PUBLICATIONS BY SUBJECT - IAEA...computed tomography) and PET (positron emission tomography). SPECT is currently being used universally in clinical practice, while PET, orignally developed

LIFE SCIENCES .............................................................................................................................................. 1

Nuclear Medicine (including Radiopharmaceuticals) ............................................................................ 1Radiation Biology........................................................................................................................................ 2Medical Physics (including Dosimetry) .................................................................................................... 2

FOOD AND AGRICULTURE ............................................................................................................................ 4

Food Irradiation .......................................................................................................................................... 4Insect and Pest Control.............................................................................................................................. 5Mutation Plant Breeding ............................................................................................................................ 6Plant Biotechnology.................................................................................................................................... 7Soil Fertility and Irrigation.......................................................................................................................... 7Agrochemicals ............................................................................................................................................ 8Animal Production and Health .................................................................................................................. 9

NUCLEAR MEASUREMENTS, TECHNIQUES AND INSTRUMENTATION ...................................................... 11

Physics ........................................................................................................................................................ 11Dosimetry (Techniques).............................................................................................................................. 13Nuclear Analytical Techniques .................................................................................................................. 13Research Reactors and Particle Accelerators (Applications) .................................................................. 14Nuclear Data .............................................................................................................................................. 16

EARTH SCIENCES .......................................................................................................................................... 19

Uranium Geology, Exploration and Mining................................................................................................ 19Hydrology .................................................................................................................................................... 21

INDUSTRIAL APPLICATIONS .......................................................................................................................... 24

Radiation Processing.................................................................................................................................. 24Radiometry.................................................................................................................................................. 24Tracers ........................................................................................................................................................ 24

NUCLEAR AND RADIOLOGICAL SAFETY ...................................................................................................... 26

Uranium Mining and Milling ...................................................................................................................... 26Fuel Fabrication and Storage .................................................................................................................. 27Nuclear Power Plants ................................................................................................................................ 27Research Reactors .................................................................................................................................... 51Radiation Sources and Accelerators ........................................................................................................ 52Transport of Radioactive Material ............................................................................................................ 53

PUBLICATIONS BY SUBJECT

Waste Repositories .................................................................................................................................... 56Radiation Protection .................................................................................................................................. 57Accident Response .................................................................................................................................... 67Radioactive Waste Management .............................................................................................................. 72Safety Analysis ............................................................................................................................................ 77Quality Management .................................................................................................................................. 79Legal and Governmental Aspects.............................................................................................................. 79

NUCLEAR POWER.......................................................................................................................................... 81

Nuclear Power Planning and Economics .................................................................................................. 82Nuclear Power Operations ........................................................................................................................ 84Reactor Technology .................................................................................................................................... 86Quality Assurance ...................................................................................................................................... 90Qualification and Training of Personnel.................................................................................................... 91

NUCLEAR FUEL CYCLE AND WASTE MANAGEMENT .................................................................................. 93

Uranium Ore Processing ............................................................................................................................ 94Fuel Fabrication and Performance............................................................................................................ 95Spent Fuel Management............................................................................................................................ 96Waste Management .................................................................................................................................. 99

PLASMA PHYSICS AND NUCLEAR FUSION .................................................................................................. 110

SAFEGUARDS ................................................................................................................................................ 114

LEGAL MATTERS............................................................................................................................................ 116

INTERNATIONAL NUCLEAR INFORMATION SYSTEM (INIS) ........................................................................ 119

ENVIRONMENT .............................................................................................................................................. 122

PHYSICAL PROTECTION ................................................................................................................................ 131

SPECIAL PUBLICATIONS

History of the International Atomic Energy Agency: The First Forty Years ............................................ 133International Atomic Energy Agency: Personal Reflections .................................................................... 133

PERIODICALS OF THE IAEA .......................................................................................................................... 135

Nuclear Fusion Journal .............................................................................................................................. 135

INDEXES

SERIES INDEX................................................................................................................................................ 137

Technical Reports Series .......................................................................................................................... 137Safety Series .............................................................................................................................................. 142Safety Series within the NUSS (Nuclear Safety Standards) Programme .............................................. 144Safety Practice Series within the NUSS (Nuclear Safety Standards) Programme ................................ 146Safety Standards Series ............................................................................................................................ 147Safety Reports Series ................................................................................................................................ 148INSAG Series .............................................................................................................................................. 149Radiological Assessment Reports Series ................................................................................................ 149INIS Reference Series ................................................................................................................................ 149Legal Series ................................................................................................................................................ 150

IAEA Reference Data Series ...................................................................................................................... 150IAEA Safeguards Information Series ........................................................................................................ 150Atomic and Plasma–Material Interaction Data for Fusion Series .......................................................... 151Periodicals of the IAEA .............................................................................................................................. 151

LANGUAGE INDEX ........................................................................................................................................ 153

Publications of the IAEA in French ............................................................................................................ 153Publications of the IAEA in Russian .......................................................................................................... 157Publications of the IAEA in Spanish .......................................................................................................... 161

KEYWORD AND ALPHABETICAL INDEX ........................................................................................................ 167

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LIFE SCIENCES

Nuclear Medicine (including Radiopharmaceuticals)

DEVELOPMENTS IN RADIOIMMUNOASSAY AND RELATED PROCEDURESProceedings Series

Proceedings of a symposium held in co-operation with WHO,Vienna, 26–30 August 1991. The symposium focused on recentmethodological developments which would enable laboratories indeveloping countries to upgrade their level of radioimmunoassaypractice with the aim of bridging the gap to the industrialized world.Attention was also given to the production of primary reagentsincluding monoclonal antibodies and the establishment of externalquality assessment schemes, also of particular concern to develop-ing countries. This is also the case for newly emerging techniques,including non-nuclear analytical methods, as alternatives toradioimmunoassay. The clinical papers were on public health issuesof grave socioeconomic concern such as neonatal hypothyroidismand cancer. Discussions on the future of radioimmunoassayprovided guidelines as to the most suitable directions in whichprogress in radioimmunoassay could be made.

Contents: Methodological developments; Reagent production;Tumour markers; Clinical applications; Data processing and qualitycontrol; Nuclear versus non-nuclear assay methods; Miscellaneoustopics.

STI/PUB/879 (601 pp., 180 figures; 1992) ISBN 92–0–000392–3Price: 1600 Austrian schillings (€116.28)

DYNAMIC FUNCTIONAL STUDIES INNUCLEAR MEDICINE IN DEVELOPING COUNTRIESProceedings Series

Proceedings of a symposium, Vienna, 15–19 August 1988. Thepapers deal mainly with clinical applications of dynamic functionalstudies and document some of the problems involved in setting upnuclear medicine facilities in general, and specifically for the diag-nosis of the diseases prevalent in less developed countries. Othertopics covered are quality control of equipment and the transfer ofmedical technology.

Contents: Introduction; Nuclear cardiology; Renal function studies;Thyroid; Hepatobiliary function; Gastroenterology; Brain, bone;Lung; Miscellaneous; Instruments; Quality control; Cerebral func-tion studies.

STI/PUB/786 (583 pp., 122 figures; 1989) ISBN 92–0–010089–9 Price: 1440 Austrian schillings (€104.65)

NUCLEAR MEDICINE AND RELATED RADIONUCLIDE APPLICATIONS IN DEVELOPING COUNTRIESProceedings Series

Proceedings of a symposium, Vienna, 26–30 August 1985. Thesymposium, part of a series dealing with radionuclide imaging inmedicine, was the first meeting devoted to the entire field of medicalapplications of radionuclides from the point of view of developingcountries. The proceedings include discussions of current trends inthe practice of nuclear medicine in hospitals of developing countriesand highlight the inputs required in the form of equipment, radio-pharmaceuticals and organization. Also covered are the technicalaspects of a wide variety of in vitro and in vivo medical applicationsof radionuclides, with special emphasis on quality control of theseprocedures. A special session dealt with radioimmunoassay andrelated techniques in the diagnosis of parasitic diseases.

Contents: Opening of the symposium; Radioimmunoassay andrelated techniques; Radionuclide applications in the diagnosis ofparasitic diseases; Instrumentation; Clinical nuclear medicine:Liver, bones, thyroid, cardio-vascular system, lungs, kidneys, brain;Organization of nuclear medicine services in developing countries;Training in nuclear medicine.


TOMOGRAPHY IN NUCLEAR MEDICINE ➜NEWProceedings Series

Proceedings of a symposium organized in co-operation with WHO,Vienna, 21–25 August 1995. The present status and future prospectsof nuclear medicine tomography were the main topics of discussion.The purpose of the symposium was to share experience and infor-mation on new developments and clinical applications of twopromising tomographic techniques: SPECT (single photon emissioncomputed tomography) and PET (positron emission tomography).SPECT is currently being used universally in clinical practice, whilePET, orignally developed as a technique for research, has graduallymoved from the research laboratory to the clinical environment. Thesignificant differences in nuclear medicine capabilities, especially intomography, between developed and developing countries weregiven particular attention at a panel discussion.

Contents: Plenary lecture; Instrumentation and data analysis;Tumours and infection; Bones and joints; The brain; Radio-pharmaceuticals and the kidneys; The heart; Panel summary.

STI/PUB/973 (450 pp., 117 figures; 1996)ISBN 92–0–101296–9Price: 1320 Austrian schillings (€95.93)

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Radiation Biology

NUCLEAR AND ATOMIC DATA FOR RADIOTHERAPY AND RELATED RADIOBIOLOGY Panel Proceedings Series

(See under Medical Physics, below)

Medical Physics Medical Physics (including Dosimetry)

ABSORBED DOSE DETERMINATION ➜NEWIN PHOTON AND ELECTRON BEAMS — An International Code of Practice — 2nd EditionTechnical Reports Series No. 277

This second edition contains eight additional pages, summarizingrecommended changes resulting from a review of data and proce-dures presented in the first edition. Otherwise, the report remainsunchanged. The report itself represents a step towards a universalcode advising users in Secondary Standard Dosimetry Laboratories(SSDLs) and radiation therapy centres throughout the world on howto obtain the absorbed dose from a measurement of exposure oranother appropriate quantity. As the numerical result of a physicalmeasurement must be complemented by an assessment of its uncer-tainty, Appendix A to this Code gives a brief summary of a treatmentuncertainties concept by A. Allisy and J.W. Müller from the BureauInternational des Poids et Mesures (BIPM).

Contents: 1. Introduction; 2. Radiation quantities and units;3. Equipment; 4. Radiation quality specification and determination;5. Measurement chain; 6. Formalism; 7. Determination of absorbeddose to water; 8. Details on correction factors; 9. The uncertainty inabsorbed dose determination at the reference point; 10. Evaluationof performance; Appendix A: Evaluation of uncertainties; AppendixB: Introduction to worksheets and flow diagrams.

STI/DOC/010/277/2 (98 pp., 16 figures; 1997)E ISBN 92–0–100597–0S ISBN 92–0–304198–2Price: 360 Austrian schillings (€26.16)

MEASUREMENT ASSURANCE IN DOSIMETRYProceedings Series

Proceedings of a symposium, Vienna, 24–27 May 1993. Accuratedosimetry is of great importance for applications of radiation inmedicine. The symposium covered all the various steps required inthe calibration chain to determine the absorbed dose in radiotherapy.Different calibration procedures at primary and secondary standardlaboratories were discussed, and reports were presented on doseintercomparisons based on different national and internationalprotocols. Analyses of the accuracy of various interaction coeffi-cients were also presented. The final session dealt with the specialproblems of diagnostic X ray dosimetry.

Contents: Status of primary standards for absorbed dose, exposureand kerma; Intercomparison, dissemination and transfer; Calibra-tions and quality assurance programmes; Dose, volume and qualityspecifications; Interaction coefficients and correction factors; Appli-cation of different protocols for absorbed dose determination; Planeparallel chambers; Beam quality dependence; Direct calibration inabsorbed dose to water; Diagnostic X ray dosimetry.

STI/PUB/930 (691 pp., 167 figures; 1994)ISBN 92–0–100194–0 Price: 1900 Austrian schillings (€138.08)


Proceedings of an Advisory Group meeting, Rijswijk, Nether-lands,16–20 September 1985, in co-operation with the Radio-biological Institute TNO. The meeting had the following specificobjectives: to make an inventory of available knowledge on nuclearand atomic data sets relevant to radiotherapy and related radiobiol-ogy; to identify and specify further needs for nuclear and atomicdata and their accuracies; to stimulate new experimental and theo-retical work to fill the identified gaps in nuclear reaction, decay andatomic data; to formulate specific technical recommendations forfuture work.

Contents: Introduction; Applications and beam production;Neutron interactions; Pion interactions; Charged particle interac-tions; Charged particle track structure; Working groups: 1. Beamproduction and field description; 2. Dosimetry; 3. Interpretation andoptimization of biological effects.


RADIOTHERAPY IN DEVELOPING COUNTRIES Proceedings Series

Proceedings of a symposium, Vienna, 1–5 September 1986. Thesymposium gathered together specialists from developed and devel-oping countries to discuss problems involved in radiotherapy indeveloping countries, including the lack of facilities, aggravated bya severe shortage of drugs, and ways of improving the situation. Thesymposium was the first major meeting of its kind to take stock ofthe prevailing situation and to assess the magnitude of the variousproblems.

Contents: Radiation therapy for carcinoma of the cervix; Differentapproaches in radiation therapy; Hyperthermia; Chemical modifiers;Dosimetry and technology; Organization of radiation therapy indeveloping countries.


THE USE OF PLANE PARALLEL IONIZATION ➜NEWCHAMBERS IN HIGH ENERGY ELECTRONAND PHOTON BEAMS —An International Code of Practice for DosimetryTechnical Reports Series No. 381

This report both complements and extends Technical Reports SeriesNo. 277/2, Absorbed Dose Determination in Photon and ElectronBeams — An International Code of Practice, IAEA TechnicalReports Series No. 277/2. It describes options and how to calibrateplane parallel ionization chambers, against air kerma or absorbeddose to water standards at cobalt-60 gamma ray energies. The use ofthese chambers to calibrate therapy electron beams, as well as rela-tive dose measurements for photon and electron beams, is presented.This publication also updates some of the data and concepts used inTechnical Reports Series No. 277/2. It fills gaps in the latter reportwith respect to plane parallel chambers with a view to improve accu-racy in radiotherapy when these chambers are used.

Contents: 1. Introduction; 2. Update of the information in TRS-277;3. Equipment; 4. Beam quality specification; 5. NK based formalismand determination of ND,air for plane parallel ionization chambers; 6.

L I F E S C I E N C E S

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ND,w based formalism and determination of ND,w factors for planeparallel ionization chambers; 7. Use of plane parallel chambers inelectron beams; 8. Use of plane parallel chambers in photon beams;9. The uncertainty in absorbed dose determination at the referencedepth using plane parallel chambers in electron beams; 10. A codeof practice for the calibration and use of plane parallel ionizationchambers; Appendix A: Examples; Appendix B: Stopping powerratios in clinical electron beams; Appendix C: Chamber perturbationfactors in electron and photon beams.

STI/DOC/010/381 (125 pp., 21 figures; 1997)ISBN 92–0–104896–3Price: 440 Austrian schillings (€31.98)

M E D I C A L P H Y S I C S ( I N C L U D I N G D O S I M E T R Y )

NUCLEAR TECHNIQUES IN FOOD AND AGRICULTURE

Food IrradiationACCEPTANCE, CONTROL OF AND TRADE IN IRRADIATED FOODProceedings Series

Proceedings of a conference jointly organized by FAO, WHO, IAEAand the International Trade Centre UNCTAD/GATT, Geneva,12–16 December 1988. This publication contains discussions on thekey issues of the wholesomeness of irradiated food, the contributionof this technology to public health, food security and internationaltrade, the control of the process to ensure its correct application forconsumer protection, and the acceptance of irradiated food by indus-try and consumers. The proceedings include the International Docu-ment on Food Irradiation, highlighting the major issues related tothe acceptance of irradiated food by consumers, governmental andintergovernmental activities, the control of the process, and trade.

Contents: Opening addresses; Keynote addresses; InternationalDocument on Food Irradiation; Statements by official participantson behalf of their governments; Statements by observers concerningthe International Document; Closing remarks.

The International Document on Food Irradiation is reproduced inEnglish, French, Russian and Spanish.

STI/PUB/788 (204 pp., 1 figure; 1989)ISBN 92–0–010189–5Price: 580 Austrian schillings (€42.15)

ASIAN REGIONAL CO-OPERATIVE PROJECT ON FOOD IRRADIATION PHASE II: TECHNOLOGY TRANSFER Panel Proceedings Series

This publication includes the final reports of work carried out bydifferent institutions under the scope of the Asian Regional Co- oper-ative Project on Food Irradiation (RPFI), Phase II, which werepresented at the final FAO/IAEA research co-ordination meeting,Bangkok, Thailand, 31 October to 4 November 1988. Phase I of theAsian RPFI programme demonstrated the technoeconomic feasibil-ity of irradiation for processing of food items of economic impor-tance to the region, e.g. mangoes, fishery products, onions and spices.Effective transfer of food irradiation technology to the industry in theregion was implemented in Phase II, resulting in successful markettestings of several irradiated food items, e.g. potatoes, onions, garlic,dried fish, spices, apples, oranges, Chinese sausages and Thaifermented sausages. Under Phase II, which was carried out from1985 to 1988, the following objectives were covered: (1) disinfesta-tion and decontamination of stored products; (2) improvement in thehygiene of processed seafood; (3) insect disinfestation of fruits forquarantine purposes; and (4) sprout inhibition of root crops.


COMBINATION PROCESSES ➜NEWFOR FOOD IRRADIATIONPanel Proceedings Series

Proceedings of a final research co-ordination meeting of the finalresearch co-ordination programme on irradiation in combinationwith other processes for improving food quality organized by theJoint FAO/IAEA Division of Nuclear Techniques in Food and Agri-culture, Pretoria, South Africa, 27 February to 3 March 1995. Theproceedings contain the most up to date information on the use ofirradiation in combination with other food processes for (1) a signif-icant extension of the shelf-life of meat, fish, fruits and vegetables;(2) enhanced microbiological safety of fresh and processed food,including prepared meals; (3) expansion of the range of food irradi-ation applications, from individual food items to ready to eat foodand shelf-stable meals; and (4) a reduction in energy requirementsfor food processing.


COST–BENEFIT ASPECTS OF FOOD IRRADIATION PROCESSINGProceedings Series

Proceedings of a symposium jointly organized by the IAEA, FAOand WHO, Aix-en-Provence, 1–5 March 1993. Natural isotopes areamong the most powerful tools for investigating past and currentenvironmental changes. The purpose of the symposium was to eval-uate the costs and benefits of irradiation for treating various fooditems either alone or in combination with other processes. The eval-uation covered applications of the technology in terms of reducingfood losses as well as the possible economic impact of irradiation incontrolling or reducing certain food-borne illnesses and in expand-ing trade in certain food items. Discussion focused on the economicbenefits of irradiation to control a number of food-borne diseases,especially those originating from the consumption of food of animalorigin, and on the potential economic benefit from radiation as aquarantine treatment for fresh fruits and vegetables.

Contents: Keynote address; Food safety; Food losses; Irradiationfacilities; Food trade; Technology transfer; Commercial and newapplications.


INSECT DISINFESTATION OF FOOD AND AGRICULTURAL PRODUCTS BY IRRADIATIONPanel Proceedings Series

Proceedings of the final research co-ordination meeting, Beijing,China, 25–29 May 1987. The proceedings contain the results of the

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investigations presented by the participants of the Co-ordinatedResearch Programme, and include a review of the papers and asummary of the conclusions and recommendations. The papers dealwith radiation disinfestation of cereals, beans, pulses, oilseeds,copra, dates and tobacco leaves. The research findings show that theadvantages of this method are that there are no undesirable residuesin foods, no resistance developed by the insects and no significantchanges in the physicochemical properties or nutritive value of thetreated products. Another important aspect under consideration wasthe development of suitable packaging materials for controllingreinfestation of irradiated products.


RADIATION PRESERVATION OF FISH AND FISHERY PRODUCTSTechnical Reports Series No. 303

This publication includes reports of investigators under the AsianRegional Co-operative Project on Food Irradiation (RPFI), whichwas launched under the Asian Regional Co-operative Project onRadiation Preservation of Fish and Fishery Products (RCA), aproject dealing mainly with reducing losses of fish and fishery prod-ucts by applying radiation and assessing the economic feasibility ofthis technology in developing countries.

STI/DOC/10/303 (139 pp., 19 figures; 1989)ISBN 92–0–115089–XPrice: 420 Austrian schillings (€30.52)

USE OF IRRADIATION AS A QUARANTINE TREATMENT OF FOOD AND AGRICULTURAL COMMODITIESPanel Proceedings Series

Proceedings of the final research co-ordination meeting organizedby the Joint FAO/IAEA Division of Nuclear Techniques in Food andAgriculture, Kuala Lumpur, Malaysia, 27–31 August 1990. The Co-ordinated Research Programme (CRP) was initiated in 1985 with thepurpose of determining the radiation doses required to provide quar-antine security from insects and other pests infesting food and agri-cultural commodities in trade, assessing the tolerance of hostcommodities to the radiation dose(s) required to provide quarantinesecurity and distributing information on the possible use of irradia-tion as a quarantine treatment of food and agricultural commoditiesto interested parties. The results of the work carried out under thisCRP by laboratories in several countries have demonstrated thatirradiation is a viable alternative to ethylene dibromide fumigationof food. These proceedings include the final reports of work carriedout by the scientists who co-operated in this CRP, as well as reviewpapers presented at the Second Task Force Meeting on Irradiation asa Quarantine Treatment of Fresh Fruits and Vegetables held inBethesda, Maryland, USA, in January 1991.


USE OF IRRADIATION TO CONTROL INFECTIVITY OF FOOD-BORNE PARASITESPanel Proceedings Series

Proceedings of a final research co-ordination meeting, Mexico City,24–28 June 1991. The purpose of the meeting was to present theresults of the Co-ordinated Research Programme implemented in1986. These findings established conclusively the potential forapplication of food irradiation in the control of liver flukes,

tapeworms, roundworms, trichinosis, toxoplasmosis, etc. Thesummary report includes the conclusions and recommendations ofthe participating researchers.


Insect and Pest Control

EVALUATION OF GENETICALLY ALTERED ➜NEWMEDFLIES FOR USE IN STERILE INSECT TECHNIQUE PROGRAMMESPanel Proceedings Series

Proceedings of a final research co-ordination meeting held in Clear-water, Florida, 11–13 June 1994. There is an increasing use of thesterile insect technique (SIT) in control of the medfly, Ceratitis capi-tata. In the early 1980s it was recognized that the release of sterilemales only of the medfly, Ceratitis capitata (Wiedemann) wouldhave many advantages over releases of both sterile males andfemales in the application of the SIT. This stimulated the develop-ment of genetic sexing strains for the medfly mainly throughFAO/IAEA co-ordinated research programmes (CRPs). This publi-cation represents the completion of a second CRP on the subject anddemonstrates the high efficiency that is now being achieved bystrains in the field.

STI/PUB/1038 (112 pp., 22 figures; 1997)ISBN 92–0–103897–6Price: 400 Austrian shillings (€29.07)

GENETIC SEXING OF THE MEDITERRANEAN FRUIT FLYPanel Proceedings Series

Proceedings of a final research co-ordination meeting, Colymbari,Crete, 3–7 September 1988, summarizing the research and develop-ment findings of the IAEA’s programme to develop a genetic sexingmethod for the medfly by which only sterile males would bereleased. Great progress has been made in medfly genetics, includ-ing the development of experimental genetic sexing strains.

Contents: 1. Introduction; Part I: Genetics, cytogenetics and popu-lation genetics; Part II: Genetic sexing of Ceratitis capitata bymorphological, biochemical and other means; Part III: Recommen-dations, Annex and List of Participants.


LABORATORY TRAINING MANUAL ON THE USE OF NUCLEAR TECHNIQUES IN INSECT RESEARCH AND CONTROL — Third EditionTechnical Reports Serles No. 336

This manual replaces the Laboratory Training Manual on the Use ofIsotopes and Radiation in Entomology, Technical Reports SeriesNo. 61, published in 1977. An extensive revision of the isotopes partof the manual has been made and a new section on the sterile insecttechnique (SIT) has been added (including an introduction to thehistory and development of SIT, the theory and mathematicalconcepts, the general and specific requirements, case studies andlaboratory exercises). The manual is intended to help entomologistsand others responsible for the entomological research and control ofinsects in developing countries to become familiar with the potentialuse of isotopes and radiation.

F O O D I R R A D I A T I O N — I N S E C T A N D P E S T C O N T R O L

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Contents: Part I. Radiation safety; Part II. Radiation and isotopes;Part III. Radiation detection and assay of radioactivity; Part IV.Application to entomological problems; Part V. Sterile insecttechnique; Part VI. Glossary of some basic terms and concepts.


MANAGEMENT OF INSECT PESTS: NUCLEAR AND RELATED MOLECULAR AND GENETIC TECHNIQUESProceedings Series

Proceedings of a symposium jointly organized by the IAEA andFAO, Vienna, 19–23 October 1992. In the past decade significantprogress has been made in overcoming many of the difficulties ofbiologically based methods of pest management. Particularly impor-tant are the advances made in the field of molecular technology andbiotechnology. Presentations in this symposium focus on advancesand trends in insect control and eradication, genetic engineering andmolecular biology, insect genetics, operational SIT programmes, F1sterility and behaviour, biocontrol, tsetse fly R&D, and quarantine.

Contents: Genetic engineering and molecular biology; Genetics;Operational programmes; F1 sterility and insect behaviour; Biocon-trol; Research and development on the tsetse fly; Quarantine.


RADIATION INDUCED F1 STERILITY IN LEPIDOPTERA FOR AREA-WIDE CONTROL Panel Proceedings Series

Proceedings of the final research co-ordination meeting organizedby the Joint FAO/IAEA Division of Nuclear Techniques in Food andAgriculture, Phoenix, Arizona, 9–13 September 1991. Geneticcontrol of lepidopterous pests includes the environmentally benignuse of the sterile insect technique as well as the use of inheritedsterility, which is especially pronounced in the first filial (F1) gener-ation following the exposure of the parents to substerilizing doses ofionizing radiation. In the case of inherited sterility, the F1 generationis reared in the field, thereby reducing costs. Some lepidopterousspecies can be mass reared in factories, stockpiled in diapause,irradiated and activated for release in synchrony with the wild popu-lation. This method has been highly successful since 1968 inprotecting 0.5 million hectares of cotton in the San Joaquin Valley ofCalifornia from the pink bollworm. This report presents informationmainly on the inital phases in the development of the use of inher-ited sterility to manage populations of the corn earworm, codlingmoth, Asian corn borer, European corn borer, diamondback moth,cotton leafworm, fall army worm, tropical army worm, gypsy moth,pink bollworm and wild mulberry silkworm.


STERILE INSECT TECHNIQUE FOR TSETSE CONTROL AND ERADICATIONPanel Proceedings Series

Proceedings of the final research co-ordination meeting organizedby the Joint FAO/IAEA Division of Nuclear Techniques in Food andAgriculture, Vom, Plateau State, Nigeria, 6–10 June 1988. Theproceedings contain the final reports (15) of scientists co-operatingin a five year co-ordinated research programme. Its main objectiveswere: (1) to provide a research base and support for ongoing and

future tsetse control/eradication programmes involving the applica-tion of SIT; (2) to develop methods for evaluating and monitoringtsetse SIT campaigns; and (3) to develop strategies for incorporatingSIT into national and regional (area-wide) tsetse and trypanosomia-sis control programmes. Included in this volume are reports of twosuccessful SIT programmes, one in Burkina Faso covering 3000 km2

and another in Nigeria covering 1500 km2.


USE OF IRRADIATION TO CONTROL INFECTIVITY OF FOOD-BORNE PARASITESProceedings Series

(See under Food Irradiation, p. 5)

Mutation Plant Breeding

IMPROVEMENT OF GRAIN LEGUME PRODUCTION USING INDUCED MUTATIONS Panel Proceedings Series

Proceedings of a workshop, Pullman, Washington, 1–5 July 1986.The workshop concluded 35 research projects supported and co-ordinated under various programmes since 1970 which dealt withthe use of induced mutations for the genetic improvement of 15different grain legume species carried out in 21 different countries.Thus, these proceedings provide a comprehensive review of thepotential, as well as a summary of the achievements, of mutationbreeding for crop plants that are extremely important as food cropsin developing countries and as important sources of edible oil andanimal feed in developing and developed countries.

Contents: Grain legumes relevant for developing or developedcountries; Limitations of grain legume production to be lifted byimproved cultivars; Technology of mutagenesis, mutation selectionand mutant characterization for the various grain legume species;Development of mutant cultivars and their performance.


INDUCED MUTATIONS AND MOLECULARTECHNIQUES FOR CROP IMPROVEMENTProceedings Series

Proceedings of a symposium jointly organized by the IAEA andFAO, Vienna, 19–23 June 1995. The aim of the symposium was toreview current aspects of mutation and molecular biology tech-niques for use in crop improvement and to bridge the gap betweenpractical plant breeding and molecular techniques. Problems of cropimprovement worldwide, and their possible solution, werediscussed. It was concluded that use of all available approaches,including mutation and molecular biology techniques, will becrucial to future plant breeding programmes in order to meet theworld’s food production challenges.

Contents: Opening Session; Plant breeding: Problems and currenttechniques; Seed quality; Apomixis and F1 hybrids; Plant pathologyand disease resistance; Genome architecture, genome manipulationand comparative gene mapping; Methylation and gene expression;Molecular markers: Part 1: Application of DNA based marker muta-tions for improvement of cereals and other sexually reproduced cropspecies; Part 2: Use of novel DNA fingerprinting techniques for the

N U C L E A R T E C H N I Q U E S I N F O O D A N D A G R I C U L T U R E

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detection and characterization of genetic variation in vegetativelypropagated crops; Stress tolerance; Genetic transformation; Lookinginto the future: Looking into model plants; Biotechnology in devel-oping countries; Current application of mutation techniques; Mole-cular markers and genetic transformation for crop improvement(poster session); Mutation techniques and biotechnology for cropimprovement (poster session).


PLANT DOMESTICATION BY INDUCED MUTATIONPanel Proceedings Series

Proceedings of an Advisory Group meeting, Vienna, 17–21 No-vember 1986. The need for plant produced industrial raw materials, aswell as the fact that more and more people depend upon fewer andfewer plant species for their food, led scientists to consider the possi-bility of domesticating additional plant species, i.e. changing hithertonot cultivated plant species into crop plants. As spontaneous singlegene mutations contributed substantially to domestication, experimen-tal mutagenesis appears to be a promising tool to accelerate the processof domestication in new crop plants. The purpose of the meeting wasto consider the possibilities and limitations of induced mutation tech-nology for the purpose of domestication, to discuss the methodology,identify target species and define the character changes required.

STIIPUB/793 (199 pp., 12 figures; 1989)ISBN 92–0–111089–8Price: 500 Austrian schillings (€36.34)

PLANT MUTATION BREEDING FOR CROP IMPROVEMENTProceedings Series

Proceedings of a symposium jointly organized by the IAEA andFAO, Vienna, 18–22 June 1990. The technology of mutation induc-tion has been accepted by plant breeders as a valuable additionaltool for creating improved cultivars for agriculture and horticulture.It was amply demonstrated at the symposium that this technique hasbeen applied with great success in many annual seed propagatedcrops such as rice, barley, wheat, cotton, soybean and pea. The tech-nological problems identified primarily concerned vegetativelypropagated crops and, in general, the logistic difficulties in identify-ing desirable mutants in large mutagenized populations.

Contents: (Vol. 1) Opening session; Mutation breeding in particularcountries; Crop specific mutation breeding; (Vol. 2) Mutation breed-ing with particular objectives; Methodology of mutation breeding;Panel: Part 1: The role of plant breeding for the future of mankindand the need for genetic resources and opportunities for mutagene-sis or gene engineering; Part 2: Plant mutation breeding: Its futurerole, the methodology needed, training and the research priorities.

STI/PUB/842 (Vol. 1: 554 pp., 51 figures; Vol. 2: 498 pp., 91 figures; 1991) 1: ISBN 92–0–010091–02: ISBN 92–0–010191–7Price: Vol. 1: 1480 Austrian schillings (€107.56)

Vol. 2: 1320 Austrian schillings (€95.93)

Plant Biotechnology

INDUCED MUTATIONS AND MOLECULARTECHNIQUES FOR CROP IMPROVEMENTProceedings Series

(See under Mutation Plant Breeding, p. 6)

NUCLEAR TECHNIQUES AND IN VITRO CULTURE FOR PLANT IMPROVEMENTProceedings Series

Proceedings of a symposium organized by the IAEA and FAO,Vienna, 19–23 August 1985. The symposium examined the useful-ness for plant breeding purposes of somaclonal variation, i.e. theoccurrence of mutations during in vitro culture with or without theapplication of ionizing radiation or other mutagens. Another issuewas finding ways and means of maintaining the genetic integrity ofplants under in vitro conditions, such integrity being of vital impor-tance if in vitro techniques are to be used to propagate virus-freeclones of economically important plants, or to preserve germplasm ingene banks. In vitro culture techniques considerably accelerate theplant breeding cycle. This factor and the advantage of using haploidsderived from another culture were also discussed at the symposium.

Contents: Genetic variation from in vitro culture; Genetic stabilityof in vitro cultures; In vitro culture with application of mutagens;Haploids; In vitro mutant selection; Use of genetic variation derivedby in vitro culture; In vitro techniques as aids in mutation breeding;Genetic engineering.


Soil Fertility and Irrigation

NUCLEAR TECHNIQUES IN SOIL–PLANT STUDIES FOR SUSTAINABLE AGRICULTURE AND ENVIRONMENTAL PRESERVATION Proceedings Series

Proceedings of a symposium jointly organized by the IAEA andFAO, Vienna, 17–21 October 1994. The objective of the symposiumwas to assess the progress being made in the use of nuclear andrelated techniques for studying various aspects of soil fertility andplant nutrition, environmental problems, the potential and limitationsof existing methods, and the possibilities for further development.Analytical methods and equipment are discussed, as are isotope dilu-tion techniques, transfers of fixed N to non-fixing crops, crop waterconsumption, labelled fertilizer involving fertigation, 13C discrimina-tion, erosion and soil degradation, and global warming and climatechange. The proceedings should assist scientists, particularly those indeveloping countries, to find ways of increasing and sustaining soilfertility and crop production while preserving the environment.

Contents: Opening session; Recent developments in analyticalmethods and equipment; Fertilizer use and management studies;Biological nitrogen fixation in sustainable cropping systems; Soilorganic matter studies and nutrient cycling; Water use and manage-ment studies; Plant physiological aspects in crop production; Envi-ronmental pollution and preservation; Soil conservation, soil erosionand desertification; Poster session.


STABLE ISOTOPES IN PLANT NUTRITION, SOIL FERTILITY AND ENVIRONMENTAL STUDIESProceedings Series

Proceedings of a symposium jointly organized by the IAEA andFAO, Vienna, 1–5 October 1990. The objective of the symposium

M U T A T I O N P L A N T B R E E D I N G — P L A N T B I O T E C H N O L O G Y — S O I L F E R T I L I T Y A N D I R R I G A T I O N

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was to evaluate progress in the use of stable isotopes to examinevarious aspects of soil fertility and plant nutrition and some envi-ronmental problems, the potential and limitations of existingmethods, and possibilities for further development. The meetingfocused on the site level rather than the landscape level and, morespecifically, on soil–plant relations, although landscape environ-mental aspects were also examined. The underlying theme was anassessment of current and possible future approaches to two prob-lems of concern: how to increase or sustain productivity withminimum inputs, and how to limit environmental damage due toinappropriate land management and to industry.

Contents: New methodologies and approaches in stable isotopeanalysis; Measurement of biological nitrogen fixation using 15Nadditions; The 15N natural abundance method for measurement ofbiological nitrogen fixation; Review of papers in Sessions 2 and 3;Applications of 15N methods to measurement of biological nitrogenfixation; Stable isotopes in soil organic matter studies; Soil nitrogentransformations and losses; Nutrient uptake and use by the plant;Stable isotopes in studies of plant metabolism; 13C/12C discrimina-tion as a measure of water use efficiency; 13C in studies of plantcarbon balance; Stable isotopes in water transport studies; Sulphurflows and transformations in ecosystems; Atmospheric change andaerial pollutants.

STI/PUB/845 (670 pp., 137 figures; 1991)ISBN 92–0–010391–XPrice: 1800 Austrian schillings (€130.81)

Agrochemicals

ENVIRONMENTAL BEHAVIOUR OF ➜NEWCROP PROTECTION CHEMICALSProceedings Series

Proceedings of a symposium on the Use of Nuclear and RelatedTechniques for Studying Environmental Behaviour of Crop Protec-tion Chemicals jointly organized by the IAEA and FAO, Vienna,15 July 1996. Use of pesticides has become an integral componentof agricultural systems worldwide. Concerning the environment,information must be provided before a product is registered in orderto provide assurance that it can be used without unacceptable hazardto non-target organisms. In addition, post-registration surveillanceand monitoring studies are necessary to check that the fate and envi-ronmental effects of pesticides under field conditions are consistentwith predictions. Much of the data are generated using radioisotopesand other nuclear or related methods. Developing countries oftenhave to rely on data generated elsewhere in order to assess theacceptability of a compound. The purpose of the symposium was toexamine the circumstances under which extrapolation from oneenvironment to another is valid on the basis of data generated undercomparable conditions. It also considered ways in which relativelysimple methods can be used to verify the field applicability of dataobtained under sophisticated experimental conditions.

Contents: Opening session; Pesticides in the environment: Interna-tional perspective; Pesticides in the environment: Regional andcountry situations; Fate and behaviour of pesticides in the terrestrialenvironment; Fate and behaviour of pesticides in the aquatic envi-ronment; Comparison of fate and behavour of pesticides in differentenvironments; Effect of pesitcides on non-target species; Maximiz-ing the use of environmental data.


GUIDELINES FOR AGRICULTURAL COUNTERMEASURES FOLLOWING AN ACCIDENTAL RELEASE OF RADIONUCLIDESTechnical Reports Series No. 363

This report is a collation of information and experience gained fromthe Chernobyl accident in 1986, concerning the transfer of radionu-clides, especially 137Cs and 90Sr, through food chains to humans andthe ways to effectively reduce them. Accounts of measures taken invarious countries following the Chernobyl accident, which at thetime caused significant radioactive contamination of the environ-ment over widely separated areas, some relatively remote from thesite, are included.

Contents: Part I. Introduction; 1. Introduction; 2. General consider-ations; 3. Developing a strategy for agricultural countermeasures;Part II. Agricultural countermeasures: Scientific basis and practice;4. Introduction; 5. Preventive measures to be applied before andduring the arrival of radioactive fallout; 6. Countermeasures to beapplied in the first few weeks after deposition; 7. Countermeasures tobe applied in the medium and long term; 8. Losses of radionuclidesin food by processing and culinary preparation; Part III. Organizingfor response; 9. Introduction; 10. Emergency preparedness;11. Response; 12. Public information and information for farmers;Part IV. Contamination in agriculture from past nuclear accidents;13. Introduction; 14. Nuclear accident requiring countermeasuresonly in the short term; 15. Nuclear accident requiring countermea-sures in both the short and long term; Glossary.

STI/DOC/010/363 (115 pp., 1 figure; 1994)ISBN 92–0–100894–5Price: 400 Austrian schillings (€29.07)

LABORATORY TRAINING MANUAL ON THE USE OF NUCLEAR AND ASSOCIATED TECHNIQUES IN PESTICIDE RESIDUESTechnical Reports Series No. 329

The present revised manual gives a concise yet comprehensivepresentation of the basic principles necessary for the proper use ofnuclear and associated techniques in pesticide residue analysis toobtain information on the metabolism or fate of pesticide chemicalsin plants, animals, soil, water and non-target organisms.

Contents: Part I. Properties of radionuclides and radiation; Part II.Radiation detection and measurement of radioactivity; Part III.Radiation protection; Part IV. Tracer methodology; Part V. Radiationbiology; Part VI. Introduction to practical work; Part VII. Labora-tory exercises; Part Vlll. Appendices; Part IX. Glossary.


QUANTIFICATION, NATURE AND BIOAVAILABILITY OF BOUND14C-PESTICIDE RESIDUES IN SOIL, PLANTS AND FOODPanel Proceedings Series

The publication contains the papers presented at a research co-ordination meeting held in Gainesville, Florida, 25–29 March 1985.The joint FAO/IAEA programme was designed to assist scientists ofdeveloping countries to make safe and effective use of nuclear tech-niques for studying pesticide interactions with various componentsof the agricultural ecosystems. The book also contains a report onthe results of a collaborative study using a model protocol for thedetermination of bound residues in soil and appraisal of the overallprogramme accomplishments.

Contents: Papers presented by the authors; FAO/IAEA modelprotocol for the determination of bound residues in soil; Final report


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on the common experiment; Appraisal of the co-ordinated researchprogramme.


STUDIES OF THE MAGNITUDE AND NATURE OF PESTICIDE RESIDUES IN STORED PRODUCTS, USING RADIOTRACER TECHNIQUESPanel Proceedings Series

Proceedings of a final research co-ordination meeting, Ankara,30 May to 3 June 1988. The five year co-ordinated researchprogramme was established in order to aid developing MemberStates in their efforts to utilize safely and effectively pesticide chem-icals to maximize the production of grain and other stored products.The programme was designed to make safe and effective use ofradiotracer techniques for studying pesticide residues in stored prod-ucts. The present proceedings contain all papers presented at themeeting as well as model protocols for studying chemical residuesin stored products and an appraisal of the overall programmeaccomplishments.


Animal Production and Health

DOMESTIC BUFFALO PRODUCTION IN ASIAPanel Proceedings Series

Proceedings of a final research co-ordination meeting organized bythe Joint FAO/IAEA Division of Nuclear Techniques in Food andAgriculture, Rockhampton, Australia, 20–24 February 1989. Thispublication reports the results of the second five year co-ordinatedresearch programme to determine the constraints on buffalo produc-tion in terms of nutrition, reproduction and disease. Studies on nutri-tion focused on the comparative aspects of digestion of tropicalforages and crop by-products, and on the effects of supplementationor treatment of fibrous feeds. In reproduction, emphasis was placedon the evaluation of methods for overcoming prolonged postpartumanoestrus and for improving overall productivity. The studies ondiseases dealt with trypanosomiasis and rotavirus infection. Fieldoriented interdisciplinary research was stressed and many of thetrials were carried out under smallholder conditions.


FEEDING STRATEGIES FOR IMPROVING PRODUCTIVITY OFRUMINANT LIVESTOCK IN DEVELOPING COUNTRIESPanel Proceedings Series

Proceedings of a combined Advisory Group meeting and a researchco-ordination meeting, Vienna, 13–17 March 1989, with the mainobjective of reviewing developments in ruminant nutrition researchand identifying developments and techniques that could be of use todeveloping Member States in increasing livestock productivity. Theproceedings contain a selection of the papers presented at thesemeetings as well as conclusions and recommendations.


ISOTOPE AIDED STUDIES ON GOAT AND SHEEP PRODUCTION IN THE TROPICSPanel Proceedings Series

Proceedings of the final research co-ordination meeting on Improv-ing Sheep and Goat Productivity with the Aid of Nuclear Tech-niques, Perth, Australia, 20–24 February 1989, reporting the resultsof a five year co-ordinated research programme. The main objec-tives of this programme were (a) to encourage research aimed atestablishing the nutritional value of locally available feedstuffs andassessing strategies for supplementation, and (b) to examine thereproductive patterns of small ruminants in different environments,with particular emphasis on the seasonality of ovarian and testicularfunction, and the effects of nutrition and disease on reproductiveefficiency.


ISOTOPE AIDED STUDIES ON LIVESTOCK PRODUCTIVITY INMEDiTERRANEAN AND NORTH AFRICAN COUNTRIESPanel Proceedings Series

Proceedings of the final research co-ordination meeting organizedby the IAEA and the Direzione Generale per la Cooperazione Ital-iana allo Sviluppo, Rabat, Morocco, 23–27 March 1987. Theproduction of meat, milk, wool and other products from grazinganimals has a long and important tradition in countries around theMediterranean and North Africa. Although there are many millionsof both large and small ruminants in these countries, the output oflivestock products is increasingly falling short of the demandcreated by human population expansion. To reverse, or at least slowdown, this trend requires that better use be made of existing animaland feed resources — in effect to optimize individual productivity.The strategies to be adopted to optimize productivity need to bedeveloped through both basic and applied research on breeding,feeding and other management practices. Nuclear techniques,employed in conjunction with standard methods, play an importantrole in developing a proper understanding of animal/environmentinteractions; they can also be used to examine how such interactionscan be manipulated to minimize the impact of constraints andthereby to improve productivity.

Contents: Types of ruminant animals and production systems inMediterranean and North African countries; Adaptation of animalsto the environment; Reproduction and nutrition of ruminants, withfocus on indigenous breeds and feedstuffs.


ISOTOPE AIDED STUDIES ON NON-PROTEIN NITROGEN AND AGRO-INDUSTRIAL BY-PRODUCTS UTILIZATION BY RUMINANTSPanel Proceedings Series

Proceedings of the final research co-ordination meeting, Vienna,24–26 March 1986. This publication reports the results of a five-yearprogramme aimed at (1) evaluating locally available resources, inparticular agro-industrial by-products as feeds for ruminant animals,and (2) formulating rations using these resources to improve thelevel of animal production in developing countries.


A N I M A L P R O D U C T I O N A N D H E A L T H

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ISOTOPE AND RELATED TECHNIQUES IN ANIMAL PRODUCTION AND HEALTHProceedings Series

Proceedings of a symposium jointly organized by the IAEA andFAO, Vienna, 15–19 April 1991. The symposium reviewed advancesin nutrition and reproduction of ruminant and other herbivorousanimals, as well as in new approaches to disease diagnosis andcontrol. Consideration was given to isotope and related techniquescurrently employed in research, but more importantly to the appli-cation of research findings in improving the productivity of live-stock reared in tropical and subtropical developing countries, e.g. ofruminant animals whose diets mainly consist of poor qualityroughages. Also addressed were advances in the development ofhighly sensitive radioimmunoassay methods for measuring theconcentrations of reproductive and other hormones. In addition,emphasis was given to developments in the use of enzyme linkedimmunosorbent assays, not only for diagnosis of diseases of majorrelevance to developing countries, but also for their applicability inmonitoring the effectiveness of large scale vaccination programmesand conducting epidemiological surveys.

Contents: Animal nutrition; Animal reproduction; Animal health.


LIVESTOCK REPRODUCTION IN LATIN AMERICAPanel Proceedings Series

Proceedings of a final research co-ordination meeting organized bythe Joint FAO/IAEA Division of Nuclear Techniques in Food andAgriculture, Bogotá, 19–23 September 1988. The general goals ofthis programme, which was part of the ARCAL (ArreglosRegionales Cooperativos para la Promoción de la Ciencia y laTecnología Nucleares en América Latina) project, were to charac-terize and improve the reproductive management of milk, meat andfibre producing livestock maintained under the diverse environmen-tal and management conditions prevailing in the Latin Americanregion. In particular, the programme addressed the efficacy of usingradioimmunoassay methods to measure reproductive performanceon the basis of breeding and production records, behaviour and clin-ical parameters.

Contents: Part I: Milk production systems; Part I(a). Intensivedairying systems; Part I(b). Dual purpose systems; Part II. Beefproduction systems; Part III: Sheep and goat production systems;Part IV: Camelids.


NUCLEAR AND RELATED TECHNIQUES FOR IMPROVING PRODUCTIVITY OF INDIGENOUS ANIMALS IN HARSH ENVIRONMENTSPanel Proceedings Series

Proceedings of a seminar and an Advisory Group meeting, Ankara,3–8 June 1985. Although emphasis is given to the use of immunoas-say methods (RIA and EIA) for assessing reproductive status anddiagnosing infections, the publication also covers the use of radia-tion for vaccine production and radioisotopes for measuring waterand mineral requirements, and various aspects of digestion andmetabolism in ruminant livestock.

Contents: Recommendations of the FAO/IAEA Advisory Groupmeeting on Improving the Productivity of Indigenous Animals in

Harsh Environments with the Aid of Nuclear Techniques; Selectedcontributions from the seminar for developing countries in Africaand the Middle East on Research Using Techniques Aimed atImproving Meat, Milk and Wool Production from RuminantAnimals.


NUCLEAR TECHNIQUES IN THE STUDY AND CONTROL OF PARASITIC DISEASES OF LIVESTOCKPanel Proceedings Series

Proceedings of a final research co-ordination meeting, Vienna,11–14 May 1987. The aims of this programme were to encouragestudies on the development of new vaccines, or on a more extensiveapplication of the available vaccines, and to stimulate examinationof the immunology, pathogenesis and genetics of host–parasite rela-tionships of veterinary importance in developing countries.


STUDIES ON THE REPRODUCTIVE EFFICIENCY OF CATTLE USING RADIOIMMUNOASSAY TECHNIQUESPanel Proceedings Series

Proceedings of a final research co-ordination meeting, Vienna, 5–9September 1988. The 13 individual papers presented at the meetingare included in this publication and represent a synthesis of the workcarried out under the co-ordinated research programme initiated in1982 with the aim of stimulating studies to characterize and improvethe reproductive performance of indigenous cattle under the diverseenvironmental and management conditions prevailing in developingcountries.


TOWARDS LIVESTOCK DISEASE DIAGNOSIS ➜NEWAND CONTROL IN THE 21st CENTURYProceedings Series

Proceedings of a symposium on Diagnosis and Control of LivestockDiseases Using Nuclear and Related Techniques jointly organizedby the IAEA and FAO, Vienna, 7–11 April 1997. The purpose of thesymposium was to consider the application of science to livestockproduction as a complex of socioeconomic problems. It dealt notonly with the impact of developments in serology and molecularbiology, but also with questions of epidemiology, vaccines, infor-mation networks, geographical information systems and socioeco-nomic factors.

Contents: Opening session; Serological aspects; Molecular aspects;Ticks/vaccines/epidemiology; Monitoring/training; Informationtechnology/modelling; Satellites/climate; Considerations of impact;Poster presentations



NUCLEAR MEASUREMENT S, TECHNIQUES AND

INS TRUMENTATION

MEASUREMENT OF RADIONUCLIDES IN FOOD AND THE ENVIRONMENT: A Guidebook Technical Reports Series No. 295

This guidebook describes the facilities, equipment and analyticalmethods required to determine the concentrations of variousradionuclides in environmental materials and foodstuffs.

Contents: 1. Introduction; 2. Pathways and samples of interest;3. Radionuclides of interest; 4. Requirements for laboratories,equipment and personnel; 5. Collection and preparation of samples;6. Analytical methods; 7. Analytical quality control; References:Sections 1–7; Bibliography: Sections 1–7; Annex I: Method fordetermining gamma emitters; Annex II: Methods for radiochemicalanalysis of tritium; Annex IV: Methods for radiochemical analysisof plutonium, americium and curium; Annex V: Units, prefixes andsymbols; Annex VI: Nuclear accident scenarios; Annex VII:Radionuclide data; Annex VIII: Grass sample collection; Annex IX:Gamma spectrometric systems; Annex X: Potential suppliers of cali-bration sources and reference materials.

STI/DOC/10/295 (169 pp., 15 figures; 1989) ISBN 92–0–125189–0 Price: 480 Austrian schillings (€34.88)

Physics

A T O M I C A N D P L A S M A – M A T E R I A L I N T E R A C T I O N D A T A F O R F U S I O N

The purpose of this series of annually published volumes of whichthe earlier issues were supplements to the Nuclear Fusion journal isto publish original contributions and review articles containing highquality data on the atomic and plasma–material interactionprocesses of interest to thermonuclear fusion research. The scientificscope of the series includes the topics of elementary atomic collisionprocesses in fusion plasmas, involving photons, electrons, ions,atoms and molecules, the collision processes of plasma particleswith surfaces of fusion relevant materials, and thermophysical mate-rial response phenomena related to the plasma–material interactions.The review articles provide comprehensive critical analyses and setsof recommended data for a broader class of interaction processes orthermophysical response phenomena. The series represents amedium for direct exchange of expert assessed or generated atomicand plasma–material interaction data information between theatomic/material physics and fusion research communities.

ATOMIC AND PLASMA–MATERIAL INTERACTION DATA FOR FUSION, Volume 1 (Supplement to the journal Nuclear Fusion)

This first volume is devoted to the plasma–material interactionprocesses and contains critical data assessments and data collectionsfor all major particle–surface collision processes related to thepartial recycling, impurity generation and material erosion intokamak fusion devices. Apart from processes induced by particleimpact, plasma–material interaction effects related to off-normalplasma events (e.g. disruptions, runaway electron bombardment) arealso covered in this volume. A summary of the status of data infor-mation on these effects is also provided.

STI/PUB/023/APID/01 (138 pp., 87 figures, 21 × 30 cm; 1991) Price: 300 Austrian schillings (€21.80)


Volume 2 of Atomic and Plasma–Material Interaction Data forFusion is devoted to the atomic and molecular processes takingplace in the edge region of magnetically confined fusion plasmas.The comprehensive review articles included in this volume discussexhaustively the current status of the spectroscopic and collisiondata for fusion plasma edge constituents. The collision processesconsidered include: electron scattering on plasma edge neutrals,electron impact excitation and ionization of atomic and molecularions, particle impact induced dissociative and energy transfer reac-tions involving molecular hydrogen isotopes, heavy particle colli-sion processes and ion–molecule reactions. Radiative losses andelectron cooling rates for carbon and oxygen plasma impurities arealso provided.



Volume 3 of Atomic and Plasma–Material Interaction Data forFusion is devoted to atomic collision processes of helium atoms andof beryllium and boron atoms and ions in fusion plasmas. Most ofthe articles included in this volume are extended versions of thecontributions presented at the IAEA experts meetings on AtomicData for Helium Beam Fusion Alpha Particle Diagnostics and on theAtomic Database for Beryllium and Boron, held in Vienna, June1991, or have resulted from the cross-section data analyses and eval-uations performed by the working groups of these meetings. Thevolume contains reviews of the most important classes of collision

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processes of plasma particles with helium atoms and beryllium andboron ions, and comprehensive sets of recommended cross-sectiondata for these processes.



Volume 4 of Atomic and Plasma–Material Interaction Data forFusion contains the result of a critical data evaluation of the cross-sections of ground state and excited hydrogen atoms colliding withthe basic fusion plasma constituents, the electrons and protons, andwith the multiply charged ions of major plasma impurities. Theprimary purpose of the present volume is to provide a complete setof the collisional data required for the modelling of neutral hydro-gen beam penetration in a thermonuclear fusion plasma.



Volume 5 of Atomic and Plasma–Material Interaction Data forFusion is devoted to a critical review of the physical and thermo-mechanical properties of presently considered candidate plasma-facing and structural materials for next-generation thermonuclearfusion reactors. This volume should provide fusion reactor design-ers with a source of critically assessed material properties data,including information on the material response to high heat andparticle fluxes and on the thermohydrodynamic coupling withcoolants. Emphasis is given to the presentation of the most recentresults for plasma-facing reactor materials.

STI/PUB/023/APID/05 (268 pp., 197 figures, 21 × 30 cm; 1994)Price: 350 Austrian schillings (€25.44)

ATOMIC AND PLASMA–MATERIALINTERACTION DATA FOR FUSION, Volume 6(Supplement to the journal Nuclear Fusion)

Volume 6 of Atomic and Plasma–Material Interaction Data forFusion includes critical reviews and results of original experimentaland theoretical studies on inelastic collision processes among thebasic and dominant impurity constituents of fusion plasmas. Thefollowing processes are considered: electron impact excitation ofexcited helium atoms, electron impact excitation and ionization ofplasma impurity ions and atoms, electron–impurity–ion recombina-tion and excitation, ionization and electron capture in collisions ofplasma protons and impurity ions with the main fusion plasmaneutron components H, He and H2 (the latter being always presentin the plasma edge or introduced into the plasma by neutral beaminjection for heating, fuelling or diagnostic purposes).


ATOMIC AND PLASMA–MATERIAL ➜NEWINTERACTION DATA FOR FUSION, Volume 7, Part A

Volume 7 of Atomic and Plasma–Material Interaction Data forFusion is devoted to a critical review of the chemical erosion behav-

iour of fusion plasma-facing materials, in particular carbon,beryllium and tungsten. It is intended to provide fusion reactordesigners with a detailed survey and parametrization of existing,critically assessed data for the chemical erosion of plasma-facingmaterials by particle impact. This volume is the result of a five yearCo-ordinated Research Programme on “Plasma-Interaction InducedErosion of Fusion Reactor Materials” in the period 1992–1997. PartB, which is in preparation, will provide a critical review and datacompilation for physical sputtering and radiation-enhanced subli-mation induced by fusion plasma particle impact.

Contents: 1. Introduction; 2. Erosion data derived from tokamaks;3. Carbon-based materials: Selected collection of chemical erosiondata; 4. Comprehensive set of chemical erosion data from variouslaboratories; Appendix A: List of abbreviations; Appendix B: List ofanalytical fitting functions.

STI/PUB/023/APID/07/A (277 pp., 35 figures, 21 × 30 cm; 1998)Price: 400 Austrian schillings (€29.07)

ATOMIC AND PLASMA–MATERIAL ➜NEWINTERACTION DATA FOR FUSION, Volume 8

Volume 8 provides an exhaustive source of information on elasticscattering, momentum transfer and viscosity cross-sections for colli-sions of hydrogenic ions, atoms and molecules, and their isotopes,in the energy range pertinent to fusion reactor divertor plasma andextending (in its low-energy part) to collision conditions that arerelevant for astrophysics. Hydrogen ion–helium atom collisions arealso included in this volume. The reported cross-sections areobtained from extensive quantum-mechanical calculations and canbe regarded as having very high accuracy.

Contents: Part A: Introduction and theory; Part B: Ion–neutral colli-sion systems; Part C: Neutral–neutral collision systems.


NUCLEAR GEOPHYSICS AND ➜NEWITS APPLICATIONSTechnical Reports Series No. 393

This report aims at providing background information and acomprehensive account of the nature of nuclear geophysics, itsfundamentals, its objectives, its tools for investigation and its widerange of applications benefiting society and industry. It reviews theachievements and performance of nuclear geophysical measure-ments, particularly in applications to mining, industry and agricul-ture. It also analyses many of these important applications for theireconomic impact and updates the available information on nucleargeophysics by giving an account of the most relevant achievementsand concepts introduced during recent years.

Contents: 1. Introduction; 2. Fundamentals of nuclear physics;3. Parameters obtained by nuclear techniques; 4. Measurementmethods; 5. Interpretation; 6. Impact of new technology.


N U C L E A R M E A S U R E M E N T S , T E C H N I Q U E S A N D I N S T R U M E N T A T I O N

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Dosimetry (Techniques)

ABSORBED DOSE DETERMINATION IN ➜NEWPHOTON AND ELECTRON BEAMS — An International Code of Practice — 2nd EditionTechnical Reports Series No. 277

This second edition contains eight additional pages, summarizingrecommended changes resulting from a review of data and proce-dures presented in the first edition. Otherwise, the report remainsunchanged. The report itself represents a step towards a universalcode advising users in Secondary Standard Dosimetry Laboratories(SSDLs) and radiation therapy centres throughout the world on howto obtain the absorbed dose from a measurement of exposure oranother appropriate quantity. As the numerical result of a physicalmeasurement must be complemented by an assessment of its uncer-tainty, Appendix A to this Code gives a brief summary of a treatmentuncertainties concept by A. Allisy and J.W. Müller from the BureauInternational des Poids et Mesures (BIPM).

Contents: 1. Introduction; 2. Radiation quantities and units;3. Equipment; 4. Radiation quality specification and determination;5. Measurement chain; 6. Formalism; 7. Determination of absorbeddose to water; 8. Details on correction factors; 9. The uncertainty inabsorbed dose determination at the reference point; 10. Evaluationof performance; Appendix A: Evaluation of uncertainties; AppendixB: Introduction to worksheets and flow diagrams.

STI/DOC/010/277/2 (98 pp., 16 figures; 1997)E ISBN 92–0–100597–0S ISBN 92–0–304198–2Price: 360 Austrian schillings (€26.16)

GUIDELINES ON CALIBRATION OF NEUTRON MEASURING DEVICES Technical Reports Series No. 285

The majority of the existing Secondary Standard Dosimetry Labora-tories (SSDLs) were established primarily to work with X rays andgamma rays. Neutron sources are, however, increasingly beingapplied in industrial processes, research, nuclear power develop-ment and radiation biology and medicine. This publication dealsprimarily with methods of applying radioactive neutron sources forcalibration of instrumentation, and gives an indication of the space,manpower and facilities needed to fulfil the minimum requirementsof a calibration laboratory for neutron work. Its intention is to serveas a guide for centres about to start on neutron dosimetry standard-ization and calibration.

Contents: 1. Introduction; 2. Concepts of dosimetry and calibration;3. Types of calibration and test measurement; 4. Sources, equipmentand facilities; 5. Procedures and methods; 6. Calibration of beamdosimeters; 7. Reports and records; Appendix I: Basic quantities andunits; Appendix II: Glossary; Appendix III: Neutron sources;Appendix IV: Fluence to dose equivalent conversion functions;Appendix V: List of symbols; References.

STI/DOC/10/285 (76 pp., 8 figures; 1988) ISBN 92–0–115088–1Price: 250 Austrian schillings (€18.17)

HIGH DOSE DOSIMETRY FOR RADIATION PROCESSING Proceedings Series

Proceedings of a symposium, the second in its field, Vienna,5–9 November 1990. Reliable dosimetry is a key parameter forquality assurance of radiation processing and irradiated products.

The standardization of dosimetry provides a basis for the regulatoryapproval of irradiated products and for international clearance forfree trade. Papers presented at the meeting discussed the develop-ment of new techniques, the improvement of reference and routinedosimetry systems and the quality control and assurance of dosime-try, giving an authoritative account of the status of high dosedosimetry throughout the world in 1990.

Contents: General aspects; Development of dosimetry techniques;Reference dosimetry and review of dosimetry techniques; Qualitycontrol and assurance of dosimetry.


MEASUREMENT ASSURANCE IN DOSIMETRYProceedings Series

Proceedings of a symposium, Vienna, 24–27 May 1993. Accuratedosimetry is of great importance for applications of radiation inmedicine. The symposium covered all the various steps required inthe calibration chain to determine the absorbed dose in radiotherapy.Different calibration procedures at primary and secondary standardlaboratories were discussed, and reports were presented on doseintercomparisons based on different national and internationalprotocols. Analyses of accuracy of various interaction coefficientswere also presented. The final session dealt with the special prob-lems of diagnostic X ray dosimetry.

Contents: Status of primary standards for absorbed dose, exposureand kerma; Intercomparison, dissemination and transfer; Calibra-tions and quality assurance programmes; Dose, volume and qualityspecifications; Interaction coefficients and correction factors; Appli-cation of different protocols for absorbed dose determination; Planeparallel chambers; Beam quality dependence; Direct calibration inabsorbed dose to water; Diagnostic X ray dosimetry.


Nuclear Analytical Techniques

APPLICATIONS OF ISOTOPES AND RADIATION IN CONSERVATION OF THE ENVIRONMENT Proceedings Series

Proceedings of a symposium, Karlsruhe, 9–13 March 1992. Theobjective was to review present knowledge of the applications ofradiation, radioisotopes and nuclear methods of analysis in themonitoring and control of environmental pollution and in reducingemissions of environmentally toxic substances. Isotopes and radia-tion have many characteristics which enable them to make uniquecontributions to the better understanding of environmentalprocesses, as well as to directly protect the environment from theimpact of toxic substances. These kinds of application form thefocus of this volume.

Contents: Overviews of some main areas of application of nucleartechniques; Flue gas purification; Radiation processing of liquid andsolid wastes; Industrial applications; Radiotracer studies; Majoranalytical techniques and new approaches in environmental moni-toring and research; Nuclear analytical techniques and their applica-tions: 1. Atmospheric studies; 2. Studies of solid wastes, sediments

D O S I M E T R Y ( T E C H N I Q U E S ) — N U C L E A R A N A L Y T I C A L T E C H N I Q U E S

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and soils; 3. Hydrochemical and miscellaneous studies; Panel:Current problems and future trends in the use of isotopes and radia-tion for conservation of the environment.

STI/PUB/904 (699 pp., 221 figures; 1992) ISBN 92–0–000492–X Price: 1900 Austrian schillings (€138.08)

GUIDEBOOK ON RADIOISOTOPE TRACERS IN INDUSTRY Technical Reports Series No. 316

The idea of using tracers (chemical tracers, dyes, etc.) in the inves-tigation of complex physical phenomena has always attracted theattention of scientists and engineers. When radioactive isotopesbecame available it was immediately recognized that they offered analmost ideal solution to tracer selection. Extensive experience hasbeen gathered all over the world in the application of radioactivetracers in industry. This guide is devoted to reviewing the presentstatus of the tracer method as such and to its applications to thosebranches of industry which have derived large benefits from the useof this technology.

Contents: Chapter 1. Introduction; Chapter 2. The concept oftracers; Chapter 3. General tracer technology; Chapter 4. Tracermethodology; Chapter 5. General applications; Chapter 6. Casestudies; Chapter 7. Current trends in development and applications;Annexes I–VI.


HARMONIZATION OF HEALTH RELATED ➜NEWENVIRONMENTAL MEASUREMENTS USING NUCLEAR AND ISOTOPIC TECHNIQUESProceedings Series

Proceedings of a symposium held in Hyderabad, India, 4–7 Novem-ber 1996. The aim of the symposium was to provide an internationalforum for discussion of the applications of nuclear analytical tech-niques and related isotopic tracer methods, particularly in the area ofanalytical quality assurance, including validation of analyticalmethods and development of new analytical reference materials. Asthese methodologies contribute substantially to the harmonization ofdata, they are playing an important role in the application of newlyemerging techniques such as quality management and quality assur-ance standards (e.g. ISO-25 and ISO-9000) in environmental analyt-ical laboratories. The symposium programme covered a wide varietyof applications of nuclear (and related) analytical techniques(mainly neutron activation analysis, energy dispersive X ray fluo-rescence, particle induced X ray emission and inductively coupledplasma–mass spectrometry) as used in the study of air particulates,solid waste products, sediments, food, water, human tissues,biomonitors and other kinds of environmental samples.

Contents: Quality systems and strategies; Reference materials:Production, certification and use; Nuclear analytical techniques:General aspects and quality assurance/quality control; Nuclear tech-niques and applications of quality assurance/quality control: Biolog-ical systems; Nuclear techniques and applications of quality assur-ance/quality control: Non-biological systems; Poster presentations.


NUCLEAR TECHNIQUES IN THE EXPLORATION ANDEXPLOITATION OF ENERGY AND MINERAL RESOURCES Proceedings Series

Proceedings of a symposium, Vienna, 5–8 June 1990. Over the pastdecades, many nuclear techniques have been developed and used onan industrial scale for the exploration and exploitation of energy andmineral resources, resulting in very great technical and economicbenefits. The major nuclear techniques which are currentlyemployed on a large scale include nucleonics control and on-streamanalysis, nuclear well logging and tracer investigations. The advan-tages of nuclear techniques include rapidity, relative simplicity and,in some cases, the possibility of use in hostile environments whereno other methods can be used. Furthermore, nuclear measurementsand nucleonics control can be made by non-contact processes. Thepurpose of the symposium was to review the latest concepts anddevelopments and to foster an exchange of information leading totechnology transfer from developed to developing countries.

Contents: Nucleonics control systems and on-stream analysers inthe coal industry; On-line nuclear and nuclear related analyticaltechniques in the mineral industry; Nucleonics control systems andon-stream mineral analysers; Nuclear borehole logging applications;Nuclear borehole logging instrumentation, data processing andinterpretation; Tracer techniques and radiometric methods in themineral industry; Off-line nuclear activation analysis in the mineralindustry; Summary of the panel discussion: Nuclear and nuclearrelated techniques in the mineral industry — trends and futureperspectives.


Research Reactors and Particle Accelerators (Applications)

APPLICATIONS OF ISOTOPES AND RADIATION IN CONSERVATION OF THE ENVIRONMENT

(See under Nuclear Analytical Techniques, p. 13)

CODE ON THE SAFETY OF NUCLEAR RESEARCH REACTORS: DESIGN Safety Series No. 35-S1

This publication presents international consensus principles usefulin the design of a research reactor. It is complemented by SafetySeries No. 35-S2, Code on the Safety of Nuclear Research Reactors:Operation. Both publications provide basic principles and require-ments for the safety of research reactors and critical assemblies,including the essential safety requirements for siting, quality assur-ance and regulatory control. These codes supersede the 1984 editionof Safety Series No. 35, Safe Operation of Research Reactors andCritical Assemblies.

Contents: Definitions; 1. Introduction; 2. Safety objectives;3. Regulatory supervision; 4. Siting requirements; 5. General designrequirements; 6. Specific design requirements; Appendix: Selectedpostulated initiating events; Annex: Selected safety functions.

STI/PUB/927 (44 pp., 1992) E ISBN 92–0–104292–2 F ISBN 92–0–200193–2R ISBN 92–0–400592–0S ISBN 92–0–300292–8Price: 220 Austrian schillings (€15.99)


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CODE ON THE SAFETY OF NUCLEAR RESEARCH REACTORS: OPERATION Safety Series No. 35-S2

This publication presents international consensus principles usefulin the operation of a research reactor. It is complemented by SafetySeries No. 35-S1, Code on the Safety of Nuclear Research Reactors:Design. Both publications provide basic principles and requirementsfor the safety of research reactors and critical assemblies, includingthe essential safety requirements for siting, quality assurance andregulatory control. These codes supersede the 1984 edition of SafetySeries No. 35, Safe Operation of Research Reactors and CriticalAssemblies.

Contents: Definitions; 1. Introduction; 2. Safety objectives;3. Regulatory supervision; 4. Responsibilities for safe operation;5. Safety analysis for operation; 6. Operational limits and condi-tions; 7. Operating procedures; 8. Commissioning; 9. Maintenance,period testing and inspection; 10. Core management and fuelhandling; 11. Records and reports; 12. Reactor utilization; 13. Modi-fications; 14. Radioactive wastes; 15. Radiation protection;16. Emergency planning; 17. Security; 18. Quality assurance;19. Decommissioning; Annex: Examples of operational aspects ofresearch reactors that require particular attention in a quality assur-ance programme.

STI/PUB/928 (44 pp.; 1992) E ISBN 92–0–104392–9F ISBN 92–0–200293–2R ISBN 92–0–400692–7S ISBN 92–0–300392–4 Price: 220 Austrian schillings (€15.99)

DIRECTORY OF NUCLEAR ➜NEWRESEARCH REACTORS 1998

This Directory provides administrative, technical and utilizationinformation on research reactors, operational or shut down, availablein the IAEA Research Reactor Data Base (RRDB) as of the end ofOctober 1998. General information on reactors which are planned orare under construction is also included. All information wascollected by the IAEA through questionnaires.

Contents: Part I: Operating reactors; Part II: Shut down reactors;Part III: Reactors with unverified information; Part IV: Reactorsunder construction; Part V: Planned reactors; Part VI: Decommis-sioned reactors; Part VII: Statistical summary; Part VIII: Abbrevia-tions; Part IX: Sample questionnaire.

STI/PUB/1071 (761 pp., 3 figures, 21 × 30 cm; 1998)ISBN 92–0–104998–6Price: 2520 Austrian schillings (€183.14)

MULTIPURPOSE RESEARCH REACTORS Proceedings Series

Proceedings of a symposium held in Grenoble, 19–23 October 1987.Research reactors are interdisciplinary tools that can be used in avariety of fields. They also play an important role in the support ofnational and international nuclear programmes. Purpose researchreactors with high fluxes, such as materials testing and neutronbeam reactors, have a wide application. Their efficient utilizationrequires technology groups specialized in the design and fabricationof irradiation devices, as well as dosimetry and hot cell groups topermit insertion and extraction of radioactive material and post-irra-diation examinations.

Contents: Neutron beam research and applications of neutron scat-tering; Reactor engineering; Irradiation testing of fuel and materialfor fission and fusion reactors; Research reactor utilization

programmes; Neutron capture therapy; Neutron activation analysis;Applications of small reactors in research and training.


NUCLEAR RESEARCH REACTORS ➜NEWIN THE WORLD — December 1998 EditionReference Data Series No. 3

This is the twelfth edition of Reference Data Series No. 3. Thisbooklet contains general information, as of the end of November1997, on research reactors in operation, under construction, plannedand shut down. The information is collected by the Agency throughquestionnaires sent to Member States through the designatednational correspondents.

IAEA-RDS-3/12 (119 pp., 11 figures, 9.5 × 17.5 cm; 1998)ISBN 92–0–100298–XPrice: 240 Austrian schillings (€17.44)

RADIOLOGICAL SAFETY ASPECTS OF THE OPERATION OF ELECTRON LINEAR ACCELERATORS Technical Reports Series No. 188

Electron linear accelerators are being used throughout the world inincreasing numbers in a variety of important applications. Foremostamong these is their role in the treatment of cancer. Commercialuses include non-destructive testing by radiography, food preserva-tion, product sterilization and radiation processing of materials suchas plastics and adhesives. Scientific applications include investiga-tions in radiation biology, radiation chemistry, nuclear and elemen-tary particle physics and radiation research. This manual providesauthoritative guidance in radiation protection for this important cate-gory of radiation sources.

Contents: Introduction; Uses and characteristics of electron linearaccelerators; Radiation at electron linear accelerator installations;Radiation shielding; Typical installations; Radiation monitoring andinterpretation of measurements; Requirements for an effectivesafety programme; General bibliography; Appendices.


RADIOLOGICAL SAFETY ASPECTS OF THE OPERATION OF PROTON ACCELERATORS Technical Reports Series No. 283

This report serves as a guide for the planning and implementation ofradiation protection programmes for all types of positive ion accel-erators. The basic types of accelerators are briefly described,followed by a detailed description of several installations coveringthe energy range from 10 MeV to 500 GeV. Special emphasis isgiven to the production of ionizing radiation and its transmissionthrough shielding, computer techniques for shield design, radiationmeasurement and interpretation and the radiological impact ofaccelerators on the environment. Extensive references are given sothat the book can serve as a source to the published literature.

Contents: Introduction; Characteristics of positive ion accelerators;Radiation environment of positive ion accelerators; Radiationmeasurements at accelerators; Radiation shielding; Accelerator radi-ation safety programme; Radiological environmental impact of

R E S E A R C H R E A C T O R S A N D P A R T I C L E A C C E L E R A T O R S ( A P P L I C A T I O N S )

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accelerators; Sources of information and bibliography on accelera-tor radiation protection.


SAFETY ASSESSMENT OF RESEARCH REACTORS ANDPREPARATION OF THE SAFETY ANALYSIS REPORT Safety Series No. 35-G1

This Safety Guide, a companion document to Safety Series Nos 35-S1 and 35-S2, is part of a set of publications in the IAEA SafetySeries dealing with all the important areas of research reactor safety,which includes Safety Standards, Safety Guides and Safety Prac-tices. It presents guidelines, approved by international consensus,for the preparation, review and assessment of the safety documenta-tion (Safety Series No. 35-S1) and for the preparation of the SafetyAnalysis Report (SAR) (Safety Series No. 35-S2). In addition, it ismost applicable during the design and construction stage of researchreactors, as well as during relicensing or reassessment of alreadyexisting reactors.

Contents: 1. Introduction; 2. Requirements for safety assessment inthe licensing process for a research reactor; 3. Preparation of thesafety analysis report; 4. Performance of the review and assessment;Appendix: Contents of a Safety Analysis Report; Annex I: Safetyanalysis approach and methods; Annex II: Examples of input para-meters and initial conditions; Annex III: Examples of items to beconsidered in the reactor description; Annex IV: Typical sources ofradioactive material or radiation fields in a research reactor.

STI/PUB/960 (103 pp.; 1994) ISBN 92–0–104594–8 Price: 400 Austrian schillings (€29.07)

SAFETY IN THE UTILIZATION AND MODIFICATION OF RESEARCH REACTORS Safety Series No. 35-G2

This Safety Guide, part of a set of publications in the IAEA SafetySeries dealing with all the important areas of research reactor safetywhich includes Safety Standards, Safety Guides and Safety Prac-tices, develops the general concepts presented in Safety Series Nos35-S1 and No. 35-S2 and should be read in conjunction with them.It presents guidelines, approved by international consensus, for thesafe utilization and modification of research reactors to ensure thatthese projects are implemented without undue risks to personnel, thepublic, the environment or the reactor. While the guide is mostapplicable to existing reactors, it is also recommended for use byorganizations planning to put a new reactor into operation.

Contents: 1. Introduction; 2. Organization and responsibilities;3. Safety assessment, categorization and approval routes; 4. Generaland specific safety requirements for design; 5. Pre-implementationphase of a utilization or modification project; 6. Implementationphase of a utilization or modification project; 7. Post-implementa-tion phase of a utilization or modification project; 8. Operationalsafety requirements for experiments; 9. Safety considerations in thehandling, dismantling, post-irradiation examination and disposal ofexperimental devices; 10. Safety aspects of out-of-reactor installa-tions; 11. Quality assurance of experiments and modifications;Annex I: Categorization criteria; Annex II: Justification of a project.

STI/PUB/961 (47 pp., 1 figure; 1994) ISBN 92–0–104694–4 Price: 240 Austrian schillings (€17.44)

Nuclear Data

CIAMDA 87 — An Index to the Literature of Atomic andMolecular Collision Data Relevant to Fusion Research

The CIAMDA Series attempts to provide a worldwide bibliograph-ical index of the research publications on collisions between elec-trons, photons, hydrogen isotopes and helium, as well as collisionsbetween these species and other ions, atoms and (a few) moleculesof importance in magnetic-confinement fusion research. The firstissue, CIAMDA 80, covered the period from the early 1950s to themiddle of 1979. This update extends the index from the cut-off dateof CIAMDA 80 to August 1986.

Contents: Introduction; Section I: Major data references; Section II:Data index for collisions between two partners; Section III: Bibliog-raphy for the data index; Section IV: References not included in thedata index; Section V: Author index. Appendix A: REF codes;Appendix B: Table IV. List of elements.

STI/PUB/752 (315 pp., 21 × 29.7 cm; 1987) ISBN 92–0–039087–0 Price: 430 Austrian schillings (€31.25)

CIAMDA 98 — An Index to the ➜NEWLiterature of Atomic and Molecular Collision Data Relevant to Fusion Research

The CIAMDA Series attempts to provide a worldwide bibliographicindex of the research publications on collisions between electrons,photons, hydrogen isotopes and helium, as well as collisionsbetween these species and other ions, atoms and molecules ofimportance in magnetic confinement fusion research. The biblio-graphic index in CIAMDA is also useful to researchers working inthe broader field of atomic and molecular physics. The first issue,CIAMDA 80, covers the period from the early 1950s to the middleof 1979. The second issue, CIAMDA 87, contains bibliographicreferences from the cut-off date of CIAMDA 80 to August 1986 andincludes extended indexations lines and supplementary referencecitations to non-indexed references. The present volume,CIAMDA 98, contains bibliographic references since September1986 and in addition contains a section with supplemental (non-indexed) data references.

Contents: Introduction; Section I. Data index for collisions betweentwo partners; Section II. Bibliography for the data index; Section III.Supplemental data references; Section IV. Author index;Appendix A. REF codes (reference abbreviations); Appendix B. Listof elements.

STI/PUB/1069 (635 pp., 21 × 29.7 cm; 1998)ISBN 92–0–103998–0Price: 940 Austrian schillings (€69.77)

CINDA-A (1935–1987)

An index to literature and computer files on microscopic neutrondata. It is a worldwide bibliography of the literature on microscopicneutron nuclear data resulting from experiments, theory and evalua-tions, and an index to internationally available computer libraries ofneutron data. It is thus of interest to every scientist involved in pureor applied neutron physics, such as experimental neutron physics,compilation and evaluation of neutron nuclear data, reactor physics,nuclear fusion, neutron dosimetry, radiation protection and shield-ing, irradiation in medicine and biology, radioisotope productionand neutron activation techniques. The present CINDA file containsmore than 230 000 entries. It also includes index lines for experi-mental and evaluated numerical data files available from datacentres. The entries are sorted by element, isotope and data category.


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The list of data categories comprises microscopic cross-sections,angular distributions and energy spectra from all neutron-inducedreactions of the energy range from 0 to 50 MeV and above, as wellas resonance parameters, resonance integrals, level density parame-ters, yields of fission neutrons and fission fragments, gamma rayspectra, and also a few related nuclear reactions such as spontaneousfission, photo-fission and production of photo-neutrons. CINDA-A,the archival issue in 5 volumes, contains entries from the literaturepublished between 1935 and 1987. CINDA-A is supplemented byCINDA 90, which covers the literature published from 1988 tospring 1990.

Contents: Vol. 1: Introduction; CINDA listing for collective entries‘Many’ and ‘Fprod’; Molecules and mixtures; Annex; Vol. 2:CINDA listing for 1 Hydrogen to 30 Zinc; Vol. 3: CINDA listing for31 Gallium to 54 Xenon; Vol. 4: CINDA listing for 55 Caesium to83 Bismuth; Vol. 5: CINDA listing for 84 Polonium to 105Hahnium.

CINDA-A (Rev. 1) (Vol. 1: 191 pp., Vol. 2: 923 pp., Vol. 3: 685 pp.,Vol. 4: 667 pp., Vol. 5: 675 pp.; 16.5 × 24 cm; 1990) 1: ISBN 92–0–039190–7 2: ISBN 92–0–039290–3 3: ISBN 92–0–039390–X 4: ISBN 92–0–039490–6 5: ISBN 92–0–039590–2 Price: Vol. 1: 240 Austrian schillings (€17.44)

Vol. 2: 1200 Austrian schillings (€87.21)Vol. 3: 900 Austrian schillings (€65.41)Vol. 4: 900 Austrian schillings (€65.41)Vol. 5: 900 Austrian schillings (€65.41)

CINDA 97 (1988–1997) ➜NEWCINDA 97 is an index to the literature on neutron nuclear datapublished after 1987. It supersedes the previous issues CINDA 95and CINDA 96 (Supplement to CINDA 95). The complete CINDAfiles as of 1 June 1997 are contained in the archival issue CINDA-A(1990) plus the current issue CINDA 97.

CINDA 97 (561 pp; 1997)ISBN 92–0–101897–5Price: 840 Austrian schillings (€61.05)

CINDA 99 — Supplement 2 to ➜NEWCINDA 97 (1988–1999)

CINDA 99 is the second supplement to CINDA 97, an index to theliterature on neutron nuclear data published after 1987. It supersedesthe first supplement, CINDA 1998. The complete CINDA file as of1 June 1999 is contained in the archival issue CINDA-A (5 volumes,1990) plus CINDA 97 and the present issue CINDA 99.

CINDA 99 (178 pp; 1999)ISBN 92–0–102399–5Price: 310 Austrian schillings (€22.53)

COMPENDIUM OF NEUTRON SPECTRA AND DETECTOR RESPONSES FOR RADIATION PROTECTION PURPOSES Technical Reports Series No. 318

A wide variety of radiation dosimeters and survey instruments areused to monitor exposure to neutrons. To establish an adequate

neutron monitoring programme and to evaluate dosimetry resultsproperly, it is important to know both the energy distribution of theneutrons encountered and the energy dependent response of themeasuring devices. It is also important for calibration to use suchneutron fields whose spectra are appropriate for the particular appli-cation. This compendium includes a collection of neutron spectraencountered in various occupational environments and the spectra ofcalibration neutron sources. It also gives the response functions ofvarious neutron dosimeters and survey instruments. Finally, itincludes the calculated energy responses for each of the detectorsand spectra given.

Contents: Chapter 1. Introduction; Chapter 2. Dosimetric quanti-ties; Chapter 3. Dosimeters and survey instrument response func-tions; Chapter 4. Calibration neutron spectra; Chapter 5. Operationalspectra; Chapter 6. Monoenergetic neutrons incident on ellipticalphantom.

The neutron fluence to dose conversion factor, detector responsesand spectra tabulated are available on diskette from: Division ofPublications, International Atomic Energy Agency, P.O. Box 100,A-1400 Vienna, Austria.


HANDBOOK ON NUCLEAR ACTIVATION DATATechnical Reports Series No. 273

The contents of this Handbook are, in general, similar to IAEATechnical Reports Series No. 156, Handbook on Nuclear ActivationCross-Sections, published in 1974. However, there are severalimportant changes in this version, besides the inclusion of morerecent data. For example, in Part 1, all the necessary information onstandard reference data is now included.

Contents: Part 1. Standard reference data: 1–1. Nuclear properties;1–2. Standard monitor reactions for neutrons; 1–3. Production ofmonoenergetic neutrons between 0.1 and 23 MeV: Neutron energiesand cross-sections; 1–4. The neutron spectrum of spontaneousfission of californium-252; 1–5. Decay data for radionuclides usedas calibration standards. Part 2. Neutron activation: 2–1. Thermalneutron cross-sections and infinite dilution resonance integrals; 2–2.Data for 14 MeV neutron activation analysis; 2–3. Activation cross-sections induced by fast neutrons; 2–4. Californium-252 spectrumaveraged neutron cross-sections. Part 3. Charged particle activation:3–1. Calculation of excitation functions for charged particle inducedreactions; 3.–2. Activation cross-sections for elements from lithiumto sulphur; 3–3. Thick target yields for the production of radioiso-topes. Part 4. Photonuclear activation: 4–1. Photonuclear cross-sections.


HANDBOOK ON NUCLEAR DATA FOR BOREHOLE LOGGING AND MINERAL ANALYSIS Technical Reports Series No. 357

This handbook is a compendium of nuclear data to be used forneutron borehole logging and neutron activation analysis of mineralsamples, meeting the major requirements of the nuclear geophysicscommunity for microscopic cross-section and decay data.

Contents: Chapter 1. Introduction; Chapter 2. Table of nuclides;Chapter 3. Prompt gamma rays from thermal neutron capture —

N U C L E A R D A T A

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Extracted from the database; Chapter 4. Nuclear decay gamma rayswith intensities higher than 5% — An extract from the ENSDFradioactivity database; Chapter 5. Spectra of neutron sources;Chapter 6. Neutron induced reaction cross-section data for nuclidesrequired for borehole logging and mineral analysis; Chapter7. Neutron source averaged cross sections.

STI/DOC/10/357 (231 pp. + 1 diskette containing approx. 100 pp.,78 figures; 1993) ISBN 92–0–102393–6Price: 1000 Austrian schillings (€72.67)


Proceedings of an Advisory Group meeting, Rijswijk, Netherlands,16–20 September 1985, in co-operation with the RadiobiologicalInstitute TNO. The meeting had the following specific objectives: tomake an inventory of available knowledge on nuclear and atomicdata sets relevant to radiotherapy and related radiobiology; to iden-tify and specify further needs for nuclear and atomic data and theiraccuracies; to stimulate new experimental and theoretical work tofill the identified gaps in nuclear reaction, decay and atomic data; toformulate specific technical recommendations for future work.

Contents: Introduction; Applications and beam production;Neutron interactions; Pion interactions; Charged particle interac-tions; Charged particle track structure; Working groups: 1. Beamproduction and field description; 2. Dosimetry; 3. Interpretation andoptimization of biological effects.


RECOMMENDED DATA ON ATOMIC COLLISION PROCESSESINVOLVING IRON AND ITS IONS Nuclear Fusion — Special Supplement 1987

This publication contains recommendations given by a group ofexperts who attended an Advisory Group meeting in Vienna,18–20 September 1985. The purpose of the meeting was to reviewthe available atomic collision data relevant to fusion plasma model-ling, with emphasis on processes involving iron and its ions. Thefourteen experts from five Member States reviewed the status of datain the relevant areas of atomic physics and made specific recom-mendations regarding the use of these data.

Contents: R.A Phaneuf, R.K. Janev, H.T. Hunter: Charge exchangeprocesses involving iron ions; M.S. Pindzola, D.C. Griffin,C. Bottcher, S.M. Younger, H.T. Hunter: Electron impact ionizationdata for the iron isonuclear sequence; A.E. Kingston, M.A. Lennon:Electron excitation rates for iron ions.

STI/PUB/023/SPS/1987 (131 pp., 44 figures, 21 × 29.7 cm; 1987)ISBN 92–0–139087–4 Price: 280 Austrian schillings (€20.35)


EARTH SCIENCES

Uranium Geology, Exploration and Mining

ANALYTICAL TECHNIQUES IN URANIUM EXPLORATION AND ORE PROCESSING Technical Reports Series No. 341

The purpose of this manual is to assist in the establishment of ananalytical laboratory able to perform all the basic chemical andinstrumental analyses commonly used in conjunction with uraniumexploration, and mining and ore processing activities, including thedevelopment of hydrometallurgical processes. It is intended forchemists with a general background in analytical chemistry, but withlimited experience in the analytical chemistry of uranium and ofrelated elements.

Contents: Introduction; Part I. General aspects of labora-tory operation; Chapter 1. Uranium exploration; Chapter 2. Analyt-ical requirements in uranium ore processing and process develop-ment; Chapter 3. Analytical chemistry of uranium; Chapter 4. Theuranium analytical laboratory; Chapter 5. Sample preparation;Chapter 6. Calibration methods and quality control in the uraniumanalytical laboratory; Chapter 7. Statistical techniques for chemicalanalysis and process control; References; Part II. Analyticalmethods: Method 1. Analytical procedures for fluorometric determi-nation of labile uranium; Method 2. Determination of uranium inwater using a scintrex UA-3 uranium analyser; Method 3. Determi-nation of uranium in geological materials by fluorometry; Method4. Determination of uranium, thorium and potassium by gamma rayspectrometry; Method 5. Uranium determination by the fission trackmethod; Method 6. Determination of uranium by delayed neutroncounting (DNC); Method 7. Determination of uranium in ores, rocksand mineral processing solutions by XRF analysis; Method 8. Deter-mination of uranium in ores and other samples by UV/VIS spec-trophotometry; Method 9. Determination of uranium (U3O8) inuranium mill products and ores by the lead reduction method;Method 10. Atomic emission spectroscopy methods for measure-ment of impurities in uranium; Method 11. Determination ofmolybdenum in ore samples and uranium mill products; Method12. Determination of titanium (TiO2) by UV/VIS spectrometry;Method 13. Determination of vanadium in uranium ores anduranium mill products by volumetric titration; Method 14. Ammoniadetermination in uranium process solutions; Method 15. Analysis ofmill process solutions for the ferrous/ferric iron ratio, silicon andphosphorus by various analytical techniques; Method 16. Nitrateand sulphate determinations in uranium process solutions by ionchromatography; Method 17. Determination of radium-226 in solidand liquid samples by alpha spectrometry; Appendix 1: Techniquesused for uranium determination and those used for determinationsother than uranium; Appendix 2: Laboratory safety.


CONSTRUCTION AND USE OF CALIBRATION FACILITIES FORRADIOMETRIC FIELD EQUIPMENT Technical Reports Series No. 309

This report describes facilities primarily designed for uraniumexploration instruments, but also discusses the use of these facilitiesfor the calibration of radiation protection instruments.

Contents: 1. Introduction; 2. Basic radiation geophysics; 3. Instru-ments used in radiation surveys; 4. Quantities and units; 5. Relationsbetween instrument readings and the corresponding field assayvalues; 6. Calibration systems; 7. Design considerations for calibra-tion pads; 8. Construction of calibration pads; 9. Calibration.

STI/DOC/10/309 (87 pp., 15 figures; 1989) ISBN 92–0–145189–X Price: 290 Austrian schillings (€21.08)

GEOCHEMICAL EXPLORATION FOR URANIUM Technical Reports Series No. 284

The intention has been to introduce the concepts and methods ofuranium exploration geochemistry in sufficient detail so that the usermay make effective use of the techniques.

Contents: Chapter 1. Geochemical exploration for uranium;Chapter 2. General chemistry and geochemistry of uranium; Chapter3. Exploration strategy; Chapter 4. Sample media and samplingtechniques; Chapter 5. Sample preparation and storage; Chapter 6.Geochemical analysis for uranium; Chapter 7. Data and map prepa-ration; Chapter 8. Interpretation of geochemical surveys; Annex I.Data recording instructions; Annex ll. Analytical procedures forfluorimetric determination of labile uranium.


HANDBOOK ON NUCLEAR DATA FOR BOREHOLE LOGGINGAND MINERAL ANALYSIS Technical Reports Series No. 357

This handbook is a compendium of nuclear data to be used forneutron borehole logging and neutron activation analysis of mineralsamples, meeting the major requirements of the nuclear geophysicscommunity for microscopic cross-section and decay data.

Contents: Chapter 1. Introduction; Chapter 2. Table of nuclides;Chapter 3. Prompt gamma rays from thermal neutron capture —Extracted from the database; Chapter 4. Nuclear decay gamma rayswith intensities higher than 5% — An extract from the ENSDFradioactivity database; Chapter 5. Spectra of neutron sources;

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Chapter 6. Neutron induced reaction cross-section data for nuclidesrequired for borehole logging and mineral analysis; Chapter 7.Neutron source averaged cross-sections.

STI/DOC/10/357 (231 pp. + 1 diskette containing approx. 100 pp.,78 figures; 1993) ISBN 92–0–102393–6 Price: 1000 Austrian schillings (€72.67)

METALLOGENESIS OF URANIUM DEPOSITS Panel Proceedings Series

Proceedings of a Technical Committee meeting, Vienna,9–12 March 1987. This volume brings together current knowledgeon the processes involved in the formation of the various types ofuranium deposits and helps to clarify the underlying commonfactors and principles involved. In addition, it includes reports onstudies done on various deposit types in different countries. Thereare panel discussions on three specific topics: the formation ofuranium deposits, the use of metallogenic concepts in uraniumexploration, and deposit classification schemes and models.


METHODS FOR THE ESTIMATION AND ECONOMICEVALUATION OF UNDISCOVERED URANIUM ENDOWMENT AND RESOURCES: An Instruction Manual Technical Reports Series No. 344

The present manual is part of the lAEA’s programme on guides onuranium resource assessment and supply. Its purpose is to describemethods of making numerical estimates of undiscovered uraniumendowment and of the economic potential of the uranium resources.It provides guidance on choosing the method(s) most applicable toa given situation.

Contents: 1. Introduction; 2. Geological analogy principles;3. Control areas; 4. Approaches to estimation of endowment;5. Probability considerations; 6. Limited information and subjectiveprobability; 7. Deposit density methods; 8. Mineralized rock densitymethods; 9. Crustal abundance methods; 10. Economic potentialevaluation; 11. Criteria for method selection; 12.Utilization ofresource estimates; Appendix I: Glossary; Appendix II: Selectedcontrol area descriptions and gradetonnage curves; Appendix III:Case studies.


NUCLEAR GEOPHYSICS AND ➜NEWITS APPLICATIONSTechnical Reports Series No. 393

This report aims at providing background information and acomprehensive account of the nature of nuclear geophysics, itsfundamentals, its objectives, its tools for investigation and its widerange of applications benefiting society and industry. It reviews theachievements and performance of nuclear geophysical measure-ments, particularly in applications to mining, industry and agricul-ture. It also analyses many of these important applications for theireconomic impact and updates the available information on nucleargeophysics by giving an account of the most relevant achievementsand concepts introduced during recent years.

Contents: 1. Introduction; 2. Fundamentals of nuclear physics;3. Parameters obtained by nuclear techniques; 4. Measurementmethods; 5. Interpretation; 6. Impact of new technology.


NUCLEAR TECHNIQUES IN THE EXPLORATION AND EXPLOITATION OF ENERGY AND MINERAL RESOURCES Proceedings Series

Proceedings of a symposium, Vienna, 5–8 June 1990. Over the pastfew decades, many nuclear techniques have been developed andused on an industrial scale for the exploration and exploitation ofenergy and mineral resources, resulting in great technical andeconomic benefits. The major nuclear techniques which arecurrently employed on a large scale include nucleonics control andon-stream analysis, nuclear well logging and tracer investigations.The advantages of nuclear techniques include rapidity, relativesimplicity of use and, in some cases, the possibility of use in hostileenvironments where no other methods can be used. Furthermore,nuclear measurements and nucleonics control can be made by non-contact processes. The purpose of the symposium was to review thelatest concepts and developments and to foster an exchange of infor-mation leading to technology transfer from developed to developingcountries.



PRACTICAL BOREHOLE LOGGING PROCEDURES FOR MINERAL EXPLORATION, WITH EMPHASIS ON URANIUM Technical Reports Series No. 259

Borehole logging is a basic tool in the exploration for anddelineation of uranium deposits. The radioactivity associated withthe uranium can be used for the quantitative evaluation of theuranium content of rocks intercepted by the borehole. This manualis designed to provide an explanation of such procedures in a clearand straightforward manner so as to meet the needs of fieldpractitioners.

Contents: Introduction; The borehole: Its characteristics andeffects; Gross count gamma ray logging; Resistance, resistivity andconductivity; Spontaneous potential; Density logging; Neutronlogging; Field procedures; Logging examples; Appendix 1: Calibra-tion procedure for gross count gamma ray logging; Appendix 2:Correlation factors for gross count gamma ray logging; Appendix 3:Glossary and reference data.


E A R T H S C I E N C E S

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RECOGNITION OF URANIUM PROVINCES Panel Proceedings Series

Proceedings of a Technical Committee meeting, London,18–20 September 1985. The aim of the project reported in this bookwas to cover three principal areas of interest: the general nature ofuranium provinces and their formation; the characteristics of knownuranium provinces; and implications for resource evaluation andexploration. The papers presented provide an excellent coverage ofthis topic. In addition to the papers, three panels were organized tocover the three basic themes of the meeting: Information ofprovinces, characteristics of provinces and exploration.

Contents: The general nature of uranium provinces and their forma-tion; Major uranium deposits and their characteristics; Uraniumexploration; Panel discussions.


URANIUM DEPOSITS IN ASIA AND THE PACIFIC: GEOLOGY AND EXPLORATION Panel Proceedings Series

Proceedings of a Technical Committee meeting, Jakarta, Indonesia,16–19 December 1985, and one in a series of publications dealingwith regional studies being carried out on the uranium geology andresources of the world. It provides a review of the specific explo-ration techniques that are appropriate for the geological and climaticconditions in Asia. The deposits, promising prospects and explo-ration activities in Bangladesh, China, the Indian subcontinent,Indonesia, Japan, the Republic of Korea, Malaysia, the Philippines,Sri Lanka and Thailand are described. The proceedings also includethe findings of two Working Groups on Uranium Provinces andCriteria for Favourability and on Exploration Techniques.

Contents: Review papers on uranium deposits and provinces onregional and national scales; Methods and levels of exploration inthe different countries of the region; Working Group reports.


URANIUM DEPOSITS IN MAGMATIC AND METAMORPHIC ROCKSPanel Proceedings Series

Proceedings of a Technical Committee meeting, Salamanca, Spain,29 September to 3 October 1986. Magmatic and metamorphic rockscontinue to be important sources of uranium despite the fact that inrecent years interest in them has been eclipsed by the discovery oflarger, lower cost deposits in other geological environments.However, many developing countries have geological environmentsconsisting of magmatic and metamorphic rocks favouring thesetypes of uranium deposits. Individual deposits can be quite large andeconomically competitive and constitute worthwhile explorationtargets.

Contents: General characteristics and genesis of uranium depositsin magmatic and metamorphic rocks in Europe, North America,Asia and Africa; Panel discussions.


URANIUM EXTRACTION TECHNOLOGY Technical Reports Series No. 359

The purpose of this publication is to update and expand the firstedition, which was published in 1983, and to report on advances inuranium ore processing which have taken place since. It includesbackground information about the principles of the unit operationsused in uranium ore processing and summarizes the current state ofthe art. It also seeks to preserve the technology and the operating‘know-how’ developed over the past ten years. Extensive referencesprovide sources for specific technological details.

Contents: Introduction; Part I. Uranium resources and mining tech-nology; Chapter 1. Uranium resources; Chapter 2. Mining technol-ogy; Part II. Processing technology; Chapter 3. Processing concepts;Chapter 4. Ore preparation; Chapter 5. Leaching; Chapter 6.Solid–liquid separation; Chapter 7. Solution purification; Chapter 8.Product recovery; Chapter 9. By-products; Part III. Waste manage-ment and the environment; Chapter 10. Tailings management tech-nology; Part IV. Flow sheet examples; Chapter 11. Olympic Dam;Chapter 12. Key Lake; Chapter 13. Rabbit Lake; Chapter 14.Lodève; Chapter 15. Rossing; Chapter 16. Cominak; Chapter 17.White Mesa; Chapter 18. Rosita (in situ leaching).


WORLD DISTRIBUTION OF URANIUM DEPOSITS

This is the first ever geological map of the world’s uranium depositsat a scale of 1:30 000 000. It provides information on potentialeconomic uranium deposits containing more than 500 metric tonnesof uranium with an average grade greater than 0.03% uranium. Thegeological settings and locations of 590 uranium deposits meetingthe minimum criteria are shown. Shape, colour and size of symbolson the map indicate the deposit type, operational status and size. Thenames of the reported uranium deposits are listed in the legend. It isthe most comprehensive compilation of relevant information everpublished and includes previously unavailable information onuranium deposits in eastern Europe and the former Soviet Union, aswell as in China.

The maps are available folded or rolled.

STI/PUB/997/FO (1995) ISBN 92–0–004095–0 Price: 200 Austrian schillings (€14.53)

STI/PUB/997/RO (1995) ISBN 92–0–004095–0 Price: 250 Austrian schillings (€18.17)

Hydrology

E N V I R O N M E N T A L I S O T O P E D A T A : W O R L DS U R V E Y O F I S O T O P E C O N C E N T R A T I O N I NP R E C I P I T A T I O N

is a series of Technical Reports, the first of which was published in1969, containing data collected by the IAEA/WMO Isotopes-in-Precipitation Network of national laboratories set up by the IAEA inco-operation with the World Meteorological Organization in 1953.

U R A N I U M G E O L O G Y , E X P L O R A T I O N A N D M I N I N G — H Y D R O L O G Y

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ENVIRONMENTAL ISOTOPE DATA No. 8: WORLD SURVEY OF ISOTOPE CONCENTRATION IN PRECIPITATION (1980–1983)Technical Reports Series No. 264

Contents: Introduction; Data printouts (Late reports, Notes);Numerical station index; Alphabetical station index; Appen-dix 1: Code numbers for tritium laboratories; Appendix 2: Codenumbers for deuterium and oxygen-18 laboratories.


ENVIRONMENTAL ISOTOPE DATA No. 9: WORLD SURVEY OF ISOTOPE CONCENTRATION IN PRECIPITATION (1984–1987) Technical Reports Series No. 311

Contents: Introduction; Data printouts; Numerical station index;Alphabetical station index; Appendix 1: Tritium laboratory codenumbers; Appendix 2: Deuterium and oxygen-18 laboratory codenumbers.


ENVIRONMENTAL ISOTOPE DATA No. 10: WORLD SURVEY OF ISOTOPE CONCENTRATION IN PRECIPITATION (1988–1991) Technical Reports Series No. 371

This is the tenth and latest volume in the present series. It is mainlyconcerned with the concentration of the environmental isotopes(tritium, deuterium and oxygen-18) in monthly samples of precipi-tation taken by a global network of 169 stations in the period1988–1991. Selected meteorological data, such as the amount ofprecipitation, mean water vapour pressure and surface air tempera-ture, are also presented. Data before 1988 which were unavailable atthe time of the earlier issues have also been included in the latter partof this volume as late reports. The great majority of the data comesfrom the IAEA/WMO Isotopes-in-Precipitation Network, whichwas set up by the IAEA in co-operation with WMO and sevennational laboratories. The collection of the precipitation samples iscarried out by the meteorological services in 45 countries and terri-tories. Analyses of the network samples are made in co-operatinglaboratories, a full list of which is given at the end of thispublication.

Contents: Introduction; Data printouts; Numerical station index;Alphabetical station index; Appendix 1: Laboratories which haveco-operated or are co-operating in the IAEA/WMO network;Tritium laboratories; Stable isotopes laboratories.


HYDROGEOLOGICAL INVESTIGATION OF ➜NEWSITES FOR THE GEOLOGICAL DISPOSAL OF RADIOACTIVE WASTETechnical Reports Series No. 391

This report, which has been prepared as part of the IAEAprogramme on radioactive waste disposal, discusses the approachesused in the hydrogeological investigation of repository sites. It isbased on experience gained in Member States on those rock typesconsidered as having the potential to host a repository.

Contents: 1. Introduction; 2. Geological disposal of radioactivewaste; 3. Function of the geological barrier in a disposal system;4. Focusing hydrogeological investigations; 5. Hydrogeologicalissues in disposal systems; 6. Approaches to characterization of thehydrogeological system; 7. Summary.


STATISTICAL TREATMENT OF DATA ON ENVIRONMENTAL ISOTOPES IN PRECIPITATION Technical Reports Series No. 331

This publication contains a statistical evaluation of isotope andmeteorological data accumulated during three decades of operationof the global network, Isotopes in Precipitation, jointly operated bythe IAEA with the WMO. Monthly precipitation samples and mete-orological data have been collected by the meteorological servicesof more than eighty countries. For each of the 180 stations selectedfor statistical treatment, numerical data and graphs are presented,illustrating the most characteristic features of the accumulatedisotope database.

Contents: Introduction; Statistical data; Data summary; Numericalstation index; Alphabetical station index; Laboratories which haveco-operated or are co-operating in the IAEA/WMO network.


ISOTOPE TECHNIQUES IN THE STUDY ➜NEWOF ENVIRONMENTAL CHANGEProceedings Series

Proceedings of a symposium on Isotope Techniques in the Study ofPast and Current Environmental Changes in the Hydrosphere andthe Atmosphere, Vienna, 14–18 April 1997. The symposium wasstructured in five sessions of oral presentations, a poster session anda round table discussion that focused on trends and future require-ments in isotope hydrology and on applications in climate and envi-ronmental research. The major themes covered by the presentationsincluded the use of isotopic tracers in studies of atmospheric andhydrospheric changes and of human impacts on water and the envi-ronment. Special emphasis was placed on isotopic archives ofclimatic and environmental change. Some contributions addressednew technical approaches.

Contents: Opening session; Isotopic tracers of the atmosphere;Isotopic tracers of the hydrosphere; Isotopic studies of man-madehydrological impact; Isotopic archives of climatic and environmen-tal change; New technical approaches; Poster session.


ISOTOPE TECHNIQUES IN THE STUDY OF PAST AND CURRENT ENVIRONMENTAL CHANGES IN THE HYDROSPHERE AND THE ATMOSPHERE Proceedings Series

Proceedings of a symposium, Vienna, 19–23 April 1993. Naturalisotopes are among the most powerful tools for investigating pastand current environmental changes. In particular, stable isotopeshave proved to be very useful proxy indicators of climate relatedparameters such as surface air temperature, relative humidity of theatmosphere and amount of precipitation, whereas radioactive

E A R T H S C I E N C E S

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isotopes are widely used as a dating tool. The release of radionu-clides during nuclear bomb tests permitted studies of the dynamicsof transport and mixing processes in the atmosphere. It also alloweda global tracer experiment on the hydrological and carbon cycles,which substantially contributed to better understanding of these twovital compartments of the global ecosystem. A wide spectrum ofthemes was discussed at the symposium, covering both the ‘present’and the ‘past’ of the global atmosphere/hydrosphere system. Casestudies as well as methodological aspects of various isotope tech-niques applied in both areas of research were presented.

Contents: Isotopes in atmospheric studies; Isotopes in thesoil–plants–atmosphere system; Degradation of water resources;Palaeohydrology and palaeowaters; Isotope indicators of climaticchanges; Poster presentations.


ISOTOPE TECHNIQUES IN WATER RESOURCES DEVELOPMENT Proceedings Series

Proceedings of a symposium organized in co-operation withUNESCO, Vienna, 30 March to 3 April 1987. Nuclear techniquesusing isotopes are precise tools for studying water resources. Theycan provide solutions to the problem of the origin, distribution andproperties of water in a given region, especially when they are usedin combination with other tools. The contents of these proceedingsillustrate the fact that isotope hydrology has matured. It is reportedthat the development of new nuclear techniques is enabling theapplication of isotopes in uses other than hydrology.

Contents: Thermal water studies; Groundwater dating; Hydrologyof arid and semi-arid areas; Field studies with environmentalisotopes; Precipitation–surface–groundwater relationships; Pollu-tion; Artificial tracers; Sediment transport; Poster presentations.


ISOTOPE TECHNIQUES IN WATER RESOURCES DEVELOPMENT 1991 Proceedings Series

Proceedings of a symposium organized in co-operation withUNESCO, Vienna, 11–15 March 1991. The main themes were theuse of isotope techniques in solving practical problems of waterresources assessment and development, particularly with respect togroundwater protection, and in studying environmental problemsrelated to water, including the palaeohydrological and palaeoclima-tological aspects. The oral presentations were largely concernedwith the current status and trends in groundwater dating. Theproceedings contain the papers of 37 oral and the extended synopsesof 47 poster presentations.

Contents: Interface processes between the atmosphere and thehydrosphere; Surface water and sediments; Groundwater dating:Problems and new approaches; Groundwater dating: Problems andnew approaches — methodological aspects and models; Groundwa-ter; Environmental problems and water pollution; Palaeohydrologyand palaeoclimatology; Poster presentations.


ISOTOPES IN WATER ➜NEWRESOURCES MANAGEMENTProceedings Series

Proceedings of a symposium organized in co-operation withUNESCO and held in Vienna, 20–24 March 1995. The main topicsaddressed were water resources management, with emphasis onorigin and recharge of groundwater, groundwater dynamics andpollution, modelling approaches and geothermal and palaeowaterresources. The remaining discussions were concerned with surfacewater and sediments, unsaturated zones and methodological aspects.The proceedings contain the papers of 43 oral presentations and theextended synopses of over 100 poster presentations.

Contents: (Vol. 1) Recent developments; Surface water and sedi-ments; Unsaturated zones; Origin and recharge of groundwater;(Vol. 2) Dynamics of groundwater; Groundwater pollution; Model-ling approaches; Geothermal and palaeowaters.

STI/PUB/970 (Vol. 1: 463 pp., 185 figures; Vol. 2: 530 pp.,237 figures; 1996)1: ISBN 92–0–105595–12: ISBN 92–0–100796–5Price: Vol. 1: 1360 Austrian schillings (€98.84)


STUDIES ON SULPHUR ISOTOPE VARIATIONS IN NATURE Panel Proceedings Series

Proceedings of an Advisory Group meeting, Vienna, 17–20 June1985. The variations of sulphur isotopes in natural compounds (andof oxygen isotopes in sulphates) provide a powerful method ofinvestigation in various fields of earth sciences such as hydrology,geochemistry, geothermal exploration, volcanology, oceanography,sedimentology, ore formation and environmental sciences.

Contents: Summary; Isotopic composition of dissolved oceanicsulphate; Sulphur isotopes in the water of Lake Neusiedl, Austria;Relationships between the sulphur and oxygen isotope compositionof dissolved sulphate; Sulphur and sulphate-oxygen isotopes in NewZealand geothermal systems and volcanic discharges; Isotopiccomposition and origin of sulphur compounds in groundwaters andbrines in the Po Valley (northern Italy); Two case studies on theorigin of aqueous sulphate in deep crystalline rocks; Sulphur andoxygen isotopic compositions of groundwater — and sabkha —sulphate in the Middle East; Radiolytic oxidation of sulphides andgeochemical behaviour of sulphur isotopes in uranium deposits; Onbias in 34S/32S data obtained in SO2 gas in mass spectrometry;Sulphur isotope analyses of trace sulphide and sulphate in variousmaterials using Kiba reagent.


H Y D R O L O G Y

INDUS TRIAL APPLICATIONS

Radiation Processing

APPLICATIONS OF ISOTOPES AND RADIATION IN CONSERVATION OF THE ENVIRONMENTProceedings Series

Proceedings of a symposium, Karlsruhe, 9–13 March 1992. Theobjective was to review present knowledge of the applications ofradiation, radioisotopes and nuclear methods of analysis in themonitoring and control of environmental pollution and in reducingemissions of environmentally toxic substances. Isotopes and radia-tion have many characteristics which uniquely contribute to thebetter understanding of environmental processes, as well as directlyprotect the environment from the impact of toxic substances. Thesekinds of applications form the focus of this volume.

Contents: Overviews of some main areas of application of nucleartechniques; Flue gas purification; Radiation processing of liquid andsolid wastes; Industrial applications; Radiotracer studies; Majoranalytical techniques and new approaches in environmental moni-toring and research; Nuclear analytical techniques and their applica-tions: 1. Atmospheric studies; 2. Studies of solid wastes, sedimentsand soils; 3. Hydrochemical and miscellaneous studies; Panel:Current problems and future trends in the use of isotopes and radia-tion for conservation of the environment.


HIGH DOSE DOSIMETRY FOR RADIATION PROCESSING Proceedings Series

Proceedings of a symposium, the second in its field, Vienna,5–9 November 1990. Reliable dosimetry is a key parameter forquality assurance of radiation processing and irradiated products.The standardization of dosimetry provides a basis for the regulatoryapproval of irradiated products and for international clearance forfree trade. Papers presented at the meeting discussed the develop-ment of new techniques, the improvement of reference and routinedosimetry, systems and the quality control and assurance of dosime-try, presenting an authoritative account of the status of high dosedosimetry throughout the world in 1990.

Contents: General aspects; Development of dosimetry techniques;Reference dosimetry and review of dosimetry techniques; Qualitycontrol and assurance of dosimetry.


Radiometry

GAMMA, X-RAY AND NEUTRON TECHNIQUES FOR THE COAL INDUSTRY Panel Proceedings Series

Proceedings of an Advisory Group meeting in 1984 to review thelatest developments and to make recommendations on the mostpromising areas and priorities for future research and development.Potential applications include on-line process measurement of coalash, moisture, calorific value, sulphur and elemental analyses.Improved borehole logging instruments make possible the in situdetermination of ash content and coal seam delineation for resourceassessment and for mine development planning.


Tracers

GAMMA, X-RAY AND NEUTRON TECHNIQUES FOR THE COAL INDUSTRY Panel Proceedings Series

(See under Radiometry, above)

GUIDEBOOK ON RADIOISOTOPE TRACERS IN INDUSTRYTechnical Reports Series No. 316

The idea of using tracers (chemical tracers, dyes, etc.) in the inves-tigation of complex physical phenomena has always attracted theattention of scientists and engineers. When radioactive isotopesbecame available it was immediately recognized that they offered analmost ideal solution to tracer selection. Extensive experience hasbeen gathered all over the world in the application of radioactivetracers in industry. This guide is devoted to reviewing the presentstatus of the tracer method as such and to its applications to thosebranches of industry which have derived large benefits from the useof this technology.

Contents: Chapter 1. Introduction; Chapter 2. The concept oftracers; Chapter 3. General tracer technology; Chapter 4. Tracermethodology; Chapter 5. General applications; Chapter 6. Casestudies; Chapter 7. Current trends in development and applications;Annexes I–VI.


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Proceedings of a symposium held in Hyderabad, India, 4–7 Novem-ber 1996. The aim of the symposium was to provide an internationalforum for discussion of the applications of nuclear analytical tech-niques and related isotopic tracer methods, particularly in the area ofanalytical quality assurance, including validation of analyticalmethods and development of new analytical reference materials. Asthese methodologies contribute substantially to the harmonization ofdata, they are playing an important role in the application of newlyemerging techniques such as quality management and quality assur-ance standards (e.g. ISO-25 and ISO-9000) in environmental analyt-ical laboratories. The symposium programme covered a wide varietyof applications of nuclear (and related) analytical techniques(mainly neutron activation analysis, energy dispersive X ray fluo-rescence, particle induced X ray emission and inductively coupledplasma–mass spectrometry) as used in the study of air particulates,solid waste products, sediments, food, water, human tissues,biomonitors and other kinds of environmental samples.

Contents: Quality systems and strategies; Reference materials:Production, certification and use; Nuclear analytical techniques:General aspects and quality assurance/quality control; Nuclear tech-niques and applications of quality assurance/quality control: Biolog-ical systems; Nuclear techniques and applications of quality assur-ance/quality control: Non-biological systems; Poster presentations.


NUCLEAR TECHNIQUES IN THE EXPLORATION ANDEXPLOITATION OF ENERGY AND MINERAL RESOURCES Proceedings Series

Proceedings of a symposium, Vienna, 5–8 June 1990. Over the pastdecades, many nuclear techniques have been developed and used onan industrial scale for the exploration and exploitation of energy andmineral resources, resulting in very great technical and economicbenefits. The major nuclear techniques which are currentlyemployed on a large scale include nucleonics control and on-streamanalysis, nuclear well logging and tracer investigations. The advan-tages of nuclear techniques include rapidity, relative simplicity and,in some cases, the possibility of use in hostile environments whereno other methods can be used. Furthermore, nuclear measurementsand nucleonics control can be made by non-contact processes. Thepurpose of the symposium was to review the latest concepts anddevelopments and to foster an exchange of information leading totechnology transfer from developed to developing countries.



T R A C E R S

NUCLEAR AND RADIOLOGICAL SAFET Y

TOPICAL ISSUES IN NUCLEAR, RADIATION ➜NEWAND RADIOACTIVE WASTE SAFETYProceedings Series

Proceedings of an international conference, Vienna, 31 August –4 September 1998. The objective of the conference was to foster theexchange of information on topical issues in nuclear, radiation andradioactive waste safety, with the aim of consolidating an interna-tional consensus on the current status of these issues, priorities forfuture work, and the need for strengthening international co-opera-tion, including recommendations for the IAEA’s future activities.The proceedings contain the opening session addresses, topical issuepapers, keynote presentations, current issue presentations, conclu-sions of the six technical sessions and the conference chairperson’ssummary of findings and conclusion, as well as a CD-ROM with allcontributed papers.

Contents: Opening session; Safety management; Occupationalradiation protection: Trends and developments; Backfitting, upgrad-ing and modernization of nuclear power plants; Radiological protec-tion principles for situations of chronic exposure to residual radioac-tive materials: Decommissioning and rehabilitation and reclamationof land; Radiation safety in the distant future: The issue of thedisposal of long lived waste; Regulatory strategies; Current issues;Concluding session; Summary of sessions.


Uranium Mining and Milling

METHODS FOR THE ESTIMATION AND ECONOMIC EVALUATION OF UNDISCOVERED URANIUMENDOWMENT AND RESOURCES: An Instruction ManualTechnical Reports Series No. 344

The present manual is part of the lAEA’s programme on guides onuranium resource assessment and supply. Its purpose is to describemethods of making numerical estimates of undiscovered uraniumendowment and of the economic potential of the uranium resources.It provides guidance on choosing the method(s) most applicable toa given situation.

Contents: 1. Introduction; 2. Geological analogy principles;3. Control areas; 4. Approaches to estimation of endowment;5. Probability considerations; 6. Limited information and subjectiveprobability; 7. Deposit density methods; 8. Mineralized rock densitymethods; 9. Crustal abundance methods; 10. Economic potentialevaluation; 11. Criteria for method selection; 12. Utilization ofresource estimates; Appendix I: Glossary; Appendix II: Selected

control area descriptions and gradetonnage curves; Appendix III:Case studies.


RADIATION MONITORING IN THE MINING AND MILLING OF RADIOACTIVE ORESSafety Series No. 95

Over the past decade there have been significant developments in thetechniques and methods of monitoring radon and radon daughters,thoron and thoron daughters, and radioactive dusts encountered inthe mining and milling of radioactive ores. The development of newtechniques and methods of measurement has received increasedattention owing to the fact that the efficient control of radon and itsdaughters in the mining atmosphere, particularly in undergroundmines, is a difficult task. Epidemiological studies have clearlydemonstrated that the incidence of lung cancers among undergrounduranium miners, and also among underground non-uranium minerswho were exposed to radon and radon daughters in their occupa-tions, is higher than that among the general public. This publicationis a revision of IAEA Safety Series No. 43, originally issued in1976. The revised version has been limited in coverage to radiationmonitoring and medical surveillance.

Contents: 1. Introduction; 2. Administrative requirements; 3. Mainphysical properties; 4. Strategies for monitoring programmes;5. Monitoring methods; 6. Personal monitoring; 7. Health relatedsurveillance; Annex I: The licensing process for uranium explo-ration in France; Annex II: The licensing process for uranium andthorium mine–mill facilities in Canada.


SAFE MANAGEMENT OF WASTES FROM THE MINING AND MILLING OF URANIUM AND THORIUM ORES: Code of Practice and Guide to the Code Safety Series No. 85

(See under Radioactive Waste Management, p. 74)

THE APPLICATION OF THE PRINCIPLES FOR LIMITING RELEASES OF RADIOACTIVE EFFLUENTS IN THE CASE OF THE MINING AND MILLING OF RADIOACTIVE ORES Safety Series No. 90

(See under Radiation Protection, p. 66)

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Fuel Fabrication and Storage

DESIGN OF SPENT FUEL STORAGE FACILITIES Safety Series No. 116

This guide has been developed through a series of technical meet-ings and represents an international consensus on useful design prin-ciples. These principles incorporate features which will be effectivein maintaining fuel subcritical, removing residual heat, providingradiation protection and containing radioactive materials for the life-time of the facility. It is intended for use by the nuclear power indus-try, its supporting organizations and related regulatory bodies inidentifying and managing all relevant issues on the design aspectsfor the safe interim storage of spent fuel from nuclear power plants.It complements Safety Series No. 117, Operation of Spent FuelStorage, and Safety Series No. 118, Safety Assessment for SpentFuel Storage Facilities.

Contents: 1. Introduction; 2. General guidance; 3. Specific designrequirements; 4. Auxiliary systems; 5. Quality assurance; 6. Inspec-tion and maintenance; 7. Decommissioning; Definitions.

STI/PUB/976 (50 pp.; 1994) ISBN 92–0–104994–3Price: 240 Austrian schillings (€17.44)

FUEL HANDLING AND STORAGE SYSTEMS IN NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-D10

(See under Nuclear Power Plants — NUSS programme, p. 39)

OPERATION OF SPENT FUEL STORAGE FACILITIES Safety Series No. 117

This guide has been developed through a series of technical meet-ings and represents an international consensus on useful operatingprinciples. These principles incorporate features which will be effec-tive in maintaining fuel subcritical, removing residual heat, provid-ing radiation protection and containing radioactive materials for thelifetime of the facility. It is intended for use by the nuclear powerindustry, its supporting organizations and related regulatory bodiesin identifying and managing all relevant issues on the operationalaspects for the safe interim storage of spent fuel from nuclear powerplants. It complements Safety Series No. 116, Design of Spent FuelStorage Facilities, and Safety Series No. 118, Safety Assessment forSpent Fuel Storage Facilities.

Contents: 1. Introduction; 2. Key operational activities; 3. Basicsafety considerations for operation; 4. Management; 5. Training andqualifications; 6. Commissioning; 7. Operational limits and condi-tions; 8. Operating procedures; 9. Maintenance, testing, examinationand inspection; 10. Radiation and environmental protection;11. Quality assurance; 12. Safeguards and physical protection;13. Decommissioning; Definitions.


SAFETY AND ENGINEERING ASPECTS OF SPENT FUEL STORAGE Proceedings Series

Proceedings of a symposium jointly organized with OECD/NEA,Vienna, 10–14 October 1994. The purpose of the symposium was toprovide an opportunity for the exchange of information on the stateof the art and the prospects of spent fuel storage, to discuss the

worldwide situation and the major factors influencing the nationalpolicies in this field, and to identify the most important directionsthat national efforts and international co-operation in this areashould take.

Contents: Spent fuel storage programmes; Spent fuel storage tech-nology; Licensing and safety aspects of spent fuel storage; Closingsession; Poster presentations.


Nuclear Power Plants

A COMMON BASIS FOR JUDGING THE SAFETY OF NUCLEAR POWER PLANTS BUILT TO EARLIER STANDARDS — A Report by the International Nuclear Safety Advisory Group INSAG Series No. 8

This report was prepared in response to the recommendation of theIAEA General Conference in 1992 that the Director Generaldevelop a process to provide a common basis on which the accept-able level of safety of all operating nuclear power plants built toearlier standards can be judged. This followed a recommendationmade at the IAEA Conference on ‘The Safety of Nuclear Power:Strategy for the Future’ held in September 1991. The report alsoprovides a basis for allocating responsibilities for, and deciding onthe best approach to, making a safety assessment, and for selectingcriteria to adopt in deciding on what corrective action to take.

Contents: 1. Introduction; 2. Historical background; 3. Objectivesand scope; 4. Safety standards and practices; 5. Responsibilities;6. Methods of assessment; 7. Achieving acceptable levels of safety;8. Summary and conclusions.

STI/PUB/991 (19 pp.; 1995) E ISBN 92–0–102395–2F ISBN 92–0–203196–7R ISBN 92–0–400596–3S ISBN 92–0–300396–7Price: 160 Austrian schillings (€11.63)

ADVANCES IN THE OPERATIONAL SAFETY ➜NEWOF NUCLEAR POWER PLANTSProceedings Series

Proceedings of a conference, Vienna, 4–8 September 1995. The aimof the symposium was to provide a forum for exchange on the oper-ational safety of nuclear power plants with the purpose of furtherdeveloping tools which permit a systematic comprehension ofmanagement and organizational effects on plant safety. The conceptof safety culture, the concept of probabilistic safety assessment(PSA), risk analysis and operating experience feedback programmesrepresent such tools. In using these, human factors and organiza-tional performance are of major importance. Many of these tools arecapable of further development.

Contents: Opening session; Managing and regulating saferegulation; Safety performance and lessons learned; Improvingoperational safety using probabilistic safety analysis; Enhancingsafety; Rapporteurs’ reports and closing remarks; Posterpresentations.


F U E L F A B R I C A T I O N A N D S T O R A G E — N U C L E A R P O W E R P L A N T S

28

ANALYSIS OF THE BEHAVIOUR OF ADVANCED REACTOR PRESSURE VESSEL STEELS UNDER NEUTRON IRRADIATION Technical Reports Series No. 265

The final report of an IAEA co-ordinated research programmeinvolving nine organizations in eight Member States during theperiod 1977–1983. The irradiation response of seven steels typicalof modern practice, in the form of plants, forgings and submergedarc welds supplied by worldwide suppliers, was determined underlight water reactor pressure vessel irradiation conditions.

Contents: Introduction; Scientific scope and programme goals;Standard part of phase 2 programme; Irradiation conditions; Exper-imental results; Discussion of results; Conclusions; Appendix A:List of participants in the programme; Appendix B: Materials spec-ification and identification; Appendix C: Expressions used to defineerrors in linear regression analyses; Appendix D: Summary ofexperimental data; List of symbols and abbreviations.

STI/DOC/10/265 (119 pp., 50 figures; 1986)ISBN 92–0–155186–X Price: 360 Austrian schillings (€26.16)

BALANCING AUTOMATION AND HUMAN ACTION IN NUCLEAR POWER PLANTS Proceedings Series

Proceedings of a symposium jointly organized with OECD/NEA,Munich, 9–13 July 1990. The purpose was to review developmentsand to discuss directions for future efforts. One important aspect ofnuclear safety in recent years has been the very high rate of devel-opment and subsequent introduction of computer technology. Thedata acquired by computer systems have to be presented to the oper-ator in a structured form with priorization capabilities. Furtherdevelopments of operator support systems may considerably influ-ence the interface between human control and automation. To dealwith fast transients, automation and real time simulation have to beused. For other abnormal and accident situations, human flexibilitymay be preferred. Full use must be made of all plant resources, withsystem state and success path monitoring being of special interest inaccident situations. The symposium discussed all aspects of balanc-ing problems, operating, maintenance and testing, including alllevels from information processing to full automation.

Contents: Opening session; Invited papers; Conceptions andachievements in automation; Safety implication of automation;Computerized operator support — Part I; Computerized operatorsupport — Part II; Man–machine interaction; Human factorsconsideration in automation; Accident management in automation;Future trends and needs (Panel discussion).


BASIC SAFETY PRINCIPLES FOR NUCLEAR POWER PLANTS— A Report by the International Nuclear Safety Advisory GroupSafety Series No. 75-INSAG-3

Replaced by:

BASIC SAFETY PRINCIPLES FOR NUCLEAR ➜NEWPOWER PLANTS — 75-INSAG-3 Rev. 1 — A Reportby the International Nuclear Safety Advisory GroupINSAG Series No. 12

The present report is a revision of Safety Series No. 75-INSAG-3(1988), updating the statements made on the objectives and

principles of safe design and operation for electricity generatingnuclear power plants. It includes the improvements made in thesafety of operating nuclear power plants and identifies the principlesunderlying the best current safety policies to be applied in futureplants. It presents INSAG’s understanding of the principles underly-ing the best current safety policies and practices of the nuclearpower industry.

Contents: Preamble; 1. Introduction; 2. Objectives; 3. Fundamentalprinciples; 4. Specific principles; Appendix: Illustration of defencein depth; Index of keywords.

French, Russian and Spanish editions planned.


DEFENCE IN DEPTH IN NUCLEAR SAFETY — ➜NEWA Report by the International Nuclear Safety Advisory GroupINSAG Series No. 10

The present report deals with the concept of defence in depth innuclear and radiation safety, discussing its objectives, strategy,implementation and future development. The report is intended foruse by governmental authorities and by the nuclear industry and itssupporting organizations. It is intended to stimulate discussion andto promote practical action at all levels to enhance safety.

Contents: 1. Introduction; 2. The approach to defence in depth;3. Implementation of defence in depth; 4. Enhancement of defencein depth for plants currently operating; 5. Development of defencein depth for future nuclear power plants.

STI/PUB/1013 (33 pp.; 1996)E ISBN 92-0–102596–3F ISBN 92-0–201297–0R ISBN 92-0–400798–2S ISBN 92-0–301397–0Price: 200 Austrian schillings (€14.53)

DESIGN AND CONSTRUCTION OF ➜NEWNUCLEAR POWER PLANTS TO FACILITATE DECOMMISSIONINGTechnical Reports Series No. 382

This report provides guidance on the planning for decommissioningand on the provision of relevant features at the design and construc-tion stages of nuclear power plants. Most of the informationpresented is equally applicable, however, to planning and imple-menting the decommissioning of research reactors and prototypereactors. The report will be useful in the context of backfitting andrefurbishment of existing facilities.

Contents: 1. Introduction; 2. Policy and strategy considerations;3. Radiological protection and optimization considerations; 4. Plan-ning for decommissioning; 5. Documentation and records; 6. Basicdesign aspects; 7. Design features to facilitate decommissioning;8. Conclusions; Annex I: National experience; Annex II: Problemsencountered during decommissioning; Annex III: Case study on theevaluation of decommissioning facilitating features; Glossary.


N U C L E A R A N D R A D I O L O G I C A L S A F E T Y

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DESIGN OF OFF-GAS AND AIR CLEANING SYSTEMS AT NUCLEAR POWER PLANTS Technical Reports Series No. 274

This report is aimed at: (a) quantifying airborne radionuclides in off-gas and ventilation air streams in nuclear power plants; (b) review-ing the current status and latest development trends in design fornormal operation and design basis accidents; (c) providing guide-lines for design.

Contents: Introduction; General design principles; LWR nuclearpower plants; Other types of reactors; Trends in off-gas and aircleaning system design; References; Appendix A.I: Source termspecifications for LWRs; Appendix A.II: Examples of calculationsusing the GALE code.

STI/DOC/10/274 (118 pp., 36 figures; 1987)ISBN 92–0–125187–4 Price: 360 Austrian schillings (€26.16)

DEVELOPING SAFETY CULTURE IN ➜NEWNUCLEAR ACTIVITIES — Practical Suggestions to Assist ProgressSafety Reports Series No. 11

This Safety Report supplements Safety Series No. 75-INSAG-4:Safety Culture (1991) in describing practices that have proved valu-able in establishing and maintaining a sound safety culture.

Contents: 1. Introduction; 2. Safety Culture; 3. Stages of develop-ment of safety culture; 4. General practices to develop organiza-tional effectiveness; 5. Specific practices to develop safety culture;6. Assessing progress in the development of safety culture; 7. Detec-tion of incipient weakness in safety culture; 8. Concluding remarks;Appendix I: Practices used for developing an improved safetyculture that are not specifically mentioned in INSAG-4; AppendixII: Key questions for use in discussions when trying to increaseawareness of safety culture; Appendix III: Characteristics of a goodfacilitator; Appendix IV: Safety culture screening matrix; AppendixV: Index of corrective actions.


ENGINEERING AND SCIENCE EDUCATION FOR NUCLEAR POWER: A Guidebook Technical Reports Series No. 266

The guidebook provides recommendations, based on the experienceof both developed and developing countries, for upgrading or estab-lishing national education and training capabilities in engineeringand science in order to develop qualified personnel for nuclearpower programmes. Special consideration has been given to thespecific needs and conditions of developing countries.

Contents: Introduction; 1. Important aspects of engineering andscience education for nuclear power; 2. Nuclear-orientedprogrammes in mechanical, electrical, chemical, nuclear, electronicsengineering and in radiation health physics; 3. Nuclear specializa-tion (S) programmes; 4. Undergraduate (U) and post-graduate (P)programmes in nuclear-oriented mechanical (U1, P1), electrical(U2, P2) and chemical (U3, P3) engineering and postgraduateprogramme in nuclear engineering (P4) for graduates of nuclear-oriented mechanical and electrical undergraduate programmes;5. Integrated undergraduate (U) and postgraduate (P) programmes innuclear engineering (U5, P5) and radiation health physics (U6, P6);

6. Basic nuclear science and engineering laboratory; 7. Measures forimplementing and improving engineering and science education andtraining capabilities for nuclear power personnel.


EQUIPMENT QUALIFICATION IN ➜NEWOPERATIONAL NUCLEAR POWER PLANTS: Upgrading, Preserving and ReviewingSafety Reports Series No. 3

This report is based on information presented at two IAEA Techni-cal Committee meetings held within the framework of the IAEAProject on Operational Safety Guidance in 1993 and 1994. Thedocument was prepared to provide guidance to Member States inassessing the status of equipment qualification (EQ) in operationalnuclear power plants and in preserving this status. It offers methodsand practices for activities which are necessary for a successfulimplementation of periodical safety reviews. The report should be ofvalue for all countries that are parties to the Convention on NuclearSafety, which entered into force on 24 October 1996 and stipulatesthe review and, where necessary, the upgrading of the safety ofexisting nuclear installations.

Contents: 1. Introduction; 2. Concepts and process for EQ;3. Establishing EQ and required design input; 4. Upgrading EQ inoperational nuclear power plants; 5. Preserving EQ; 6. Assessingeffectiveness of the EQ programme; Annex I: Effect of licensingassumptions and equipment locations on the scope of an EQprogramme; Annex II: Examples for developing a list of equipmentto be qualified; Annex III: Examples of EQ files and documentation;Annex IV: Evaluation of a licensee’s EQ programme for electricalequipment located in a harsh environment; Annex V: Most signifi-cant components related to EQ; Annex VI: Checklist for review oflicensee EQ documentation files; Annex VII: Physical inspectionchecklist.


EVALUATION OF THE SAFETY OF ➜NEWOPERATING NUCLEAR POWER PLANTSBUILT TO EARLIER STANDARDS — A Common Basis for JudgementSafety Reports Series No. 12

This Safety Report complements Safety Guide No. 50-SG-O12,Periodic Safety Review of Operational Nuclear Power Plants(1994). It provides practical information for the safety assessmentand judgement process for operating nuclear power plants built toearlier standards, on the basis of a comparison with current safetystandards and operational practices.

Contents: 1. Introduction; 2. Objectives of safety review; 3. Safetyjudgements; Appendix I: Safety review process; Appendix II:Current standards and practices; Appendix III: Operational processevaluation; Appendix IV: The deterministic judgement process;Appendix V: The probabilistic assessment process; Annex: Judge-ment examples.


N U C L E A R P O W E R P L A N T S

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EXAMPLES OF SAFETY CULTURE PRACTICES ➜NEWSafety Reports Series No. 1

This report illustrates the concepts and principles of safety culture asgiven in Safety Series No. 75-INSAG-4, Safety Culture — A Reportby the International Nuclear Safety Advisory Group (1991). Itprovides a small selection of examples of good and poor safety prac-tice taken from a worldwide collection of safety performance evalu-ations (e.g. IAEA Safety services, national regulatory inspections,utility audits and plant assessments). These documented evaluationscollectively provide a database of safety peformance strengths andweaknesses, and related safety culture observations.

Contents: 1. Introduction; 2. Examples of safety culture practices;3. Effecting safety culture improvement; Appendix: Safety cultureobserved by the IAEA.

STI/PUB/1039 (30 pp.; 1997)ISBN 92–0–104297–3Price: 200 Austrian schillings (€14.53)

FEEDBACK OF OPERATIONAL SAFETY EXPERIENCE FROMNUCLEAR POWER PLANTS Proceedings Series

Proceedings of a symposium jointly organized with OECD/NEA,Paris, 16–20 May 1988. Operating experience feedbackprogrammes have been extensively developed at various levelswithin the nuclear community, and their effectiveness has alsoimproved greatly as a result of: (a) the setting of more ambitiousplant targets providing greater margins in accident situations; (b) theaccess to predictive operating data, indicative of the future perfor-mance of plants; and (c) the careful assessment, or review, of pastoperating experience to promptly correct the root causes of anyadverse trends. The purpose of the symposium was to provide aforum for the detailed exchange of experience for the discussion ofvarious ways of closing the feedback loop, with the ultimate goal ofenhancing the level of operational safety at nuclear power plants.

Contents: Opening session; Methods of identification of opera-tional safety issues in nuclear power plants; Methods of analysis ofoperational safety issues; Corrective actions implemented as a resultof operating experience; Operational safety experience feedbacksystems; Panel discussion: Operational safety of nuclear powerplants — future trends; Closing session.


FIRE PROTECTION AND FIRE FIGHTING IN NUCLEAR INSTALLATIONS Proceedings Series

Proceedings of a symposium, Vienna, 27 February to 3 March 1989.Within the last decade there has been considerable development infire protection and nuclear designers now recognize its importanceat all design stages. While the principles of fire protection have beenimplemented worldwide, problems are still apparent in the descrip-tion of specific aspects of fire behaviour, material properties, systemperformance, etc. The symposium provided a forum for the discus-sion of these and other questions.

Contents: Standards and licensing; National fire safety practices;Fire safety by design; Fire fighting and a panel on: How to managereal fires once they occur; Computer fire modelling; Fire safety in

fuel cycle facilities; Fire testing of materials; Fire risk assessment;Closing statement.


GAS COOLED REACTOR DESIGN AND SAFETY Technical Reports Series No. 312

The present publication is an update of IAEA Technical ReportsSeries No. 235, Status of and Prospects for Gas-Cooled Reactors,published in 1984. It is a compilation of information based onsubmissions from Member States and is considered current as of thebeginning of 1989. It describes the status of gas cooled reactors withspecific emphasis on the design and safety characteristics of thevarious concepts that are either incorporated in operating reactors orin reactors being designed and considered for future constructionand operation.

Contents: Chapter 1. Introduction; Chapter 2. Status of inter-national gas cooled reactor development; Chapter 3. Generalfeatures of gas cooled reactors and their safety characteristics;Chapter 4. Gas cooled reactor design and safety in the UnitedKingdom; Chapter 5. Gas cooled reactor design and safety in theUnited States of America; Chapter 6. Gas cooled reactor design andsafety in Japan; Chapter 7. Gas cooled reactor design and safety inthe Union of Soviet Socialist Republics; Chapter 8. Gas cooledreactor design and safety in Switzerland; Chapter 9. Gas cooledreactor design and safety in the Federal Republic of Germany;Chapter 10. Summary; Annex: Information exchange on gas cooledreactors.


GUIDEBOOK ON THE EDUCATION AND TRAINING OF TECHNICIANS FOR NUCLEAR POWER Technical Reports Series No. 306

This guidebook describes for nuclear technicians: (1) the necessarylevel and content of conventional education and training; (2) thelevel and content of nuclear oriented education and training; (3)measures to bridge the gap between the two. The guidebook comple-ments or is supplemented by Technical Reports Series No. 200,Manpower Development for Nuclear Power, Technical ReportsSeries No. 242, Qualification of Nuclear Power Plant OperationsPersonnel, and IAEA-TECDOC-526, Appendices to the Guidebookon the Education and Training of Technicians for Nuclear Power.This guidebook seeks to assist policy makers and planners, as wellas those designing and implementing education and trainingprogrammes.

Contents: Introduction; 1. Definition of technicians; 2. Planningand implementation of the E&T of technicians for nuclear power;3. Recommended E&T requirements to enter nuclear oriented E&T;4. Education and training of teachers/trainers for a nuclear powerprogramme; 5. Functions, tasks and number of technicians in anuclear power programme; 6. Basic and specialized E&T for anuclear power programme; 7. Nuclear science and engineering labo-ratory; 8. Mechanisms for education and training implementation.



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IMPLEMENTATION AND REVIEW OF ➜NEWA NUCLEAR POWER PLANT AGEING MANAGEMENT PROGRAMMESafety Reports Series No. 15

This publication provides information on good practices relating tothe implementation and review of an ageing managementprogramme (AMP) for nuclear power plants. AMPs are umbrellatype, systematic programmes integrating plant operations, inspec-tion and maintenance and other relevant programmes.

Contents: 1. Introduction; 2. Rationale for an AMP; 3. Descriptionof an AMP; 4. The AMP model and its implementation; 5. Reviewof an AMP; Appendix I: Data collection and record keeping; Appen-dix II: Examples of unanticipated ageing phenomena addressed byageing management teams; Appendix III: Indicators of AMPeffectiveness.


IMPLEMENTATION OF QUALITY ASSURANCE CORRECTIVE ACTIONS: A Manual Technical Reports Series No. 317

(See under Quality Management, p. 79)

MAN–MACHINE INTERFACE IN THE NUCLEAR INDUSTRY Proceedings Series

Proceedings of a conference organized in co-operation with theCommission of the European Communities and OECD/NEA,Tokyo, 15–19 February 1988. The conference demonstrated that thedevelopment of computer technologies offered great potential in thedesign of future control rooms for nuclear power plants withenhanced information processing capabilities.

Contents: Opening remarks; Review of status and outlook; Humanbehaviour in plant operation; Plant personnel training; Operatorsupport; Artificial intelligence and accident management; Processcontrol and human engineering in control rooms; Robots for nuclearpower plant inspection and maintenance; Human engineering incontrols and control rooms; Transients and accident management;Robotics; Final panel; Closing remarks.


MANAGEMENT OF ABNORMAL RADIOACTIVE WASTES AT NUCLEAR POWER PLANTS Technical Reports Series No. 307

This report discusses the management of abnormal wastes at nuclearfacilities. It is intended to give guidance to nuclear power plant oper-ators on the technical means available to enable abnormal wastes tobe managed safely, and to provide assistance in the selection ofappropriate technologies and processes that can be used for abnor-mal situations. In addition, subjects such as pre-planning and provi-sions for abnormal waste management, decision making on themanagement of abnormal wastes and adequate waste characteriza-tion are also discussed.

Contents: 1. Introduction; 2. Pre-planning; 3. Abnormal wastemanagement decision making and planning; 4. Characterization ofthe wastes; 5. Decontamination; 6. Treatment of liquid wastes;7. Treatment of gaseous wastes; 8. Treatment of solid wastes;

9. Conditioning of abnormal radioactive wastes; 10. Storage, trans-port and disposal; References; Annex I: Experience with abnormalwastes and their management in selected power plants; Annex II:Examples of decision making processes in the management ofabnormal wastes.


MANAGEMENT OF OPERATIONAL ➜NEWSAFETY IN NUCLEAR POWERPLANTS — A Report by the InternationalNuclear Safety Advisory GroupINSAG Series No. 13

The present report deals with the framework necessary for safetymanagement in organizations in order to promote safety culture, bysystematically addressing the general principles underlying themanagement of operational safety and by providing guidance ongood practices. It also draws on the results of audits and reviews tohighlight shortfalls in safety management.

Contents: 1. Introduction; 2. Definition of the safety managementsystem; 3. General features of a safety management system;4. Specific safety management issues; Appendix: Safety manage-ment indicators; Annex: Some examples of the effect of deficiencesin safety management.

Chinese, French, Russian and Spanish editions planned.


MANUAL ON MAINTENANCE OF SYSTEMS AND COMPONENTS IMPORTANT TO SAFETY Technical Reports Series No. 268

This user’s manual provides Member States implementing the IAEACodes and Safety Guides (NUSS) with practical examples ofmanagement organization, good practices, methods and techniquesfor the maintenance of systems and components important to safety.It contains a detailed description of management systems, adminis-trative controls and procedures for maintenance activities and someaspects of surveillance and verification activities.

Contents: Introduction; Scope; Maintenance programme; Imple-mentation of maintenance programme; Surveillance and verificationactivities; Annex I: Examples of documents; Annex II: Descriptionsof practices.


MANUAL ON TRAINING, QUALIFICATION AND CERTIFICATION OF QUALITY ASSURANCE PERSONNELTechnical Reports Series No. 262

Examples of typical QA functions to be undertaken and the associ-ated qualification requirements, training programmes, training tech-niques and methods of certification of personnel implementing thesefunctions. Applicable to those participants in a nuclear powerproject who are associated with the establishment and implementa-tion of the various QA programmes during the life cycle of theproject.


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Contents: 1. Introduction; 2. QA programmatic and evaluationfunctions; 3. Inspection and test functions; 4. Training andqualification; 5. Maintenance of qualification; 6. Records; Annex I:Qualification; Annex II: Training; Annex III: National standards fortraining, qualification and certification; Annex IV: Examples ofpersonnel qualification record forms.


METHODOLOGY FOR THE MANAGEMENT OF AGEING OF NUCLEAR POWER PLANT COMPONENTS IMPORTANT TO SAFETY Technical Reports Series No. 338

This technical report, one of a series on the management of ageingnuclear power plants, presents methodologies for selecting plantcomponents important to safety whose ageing should be assessedand for performing ageing management studies. Although the reporthas been developed for the management of ageing of plant compo-nents important to safety, the methodology studies are applicable tocomponents important to plant life.

Contents: 1. Introduction; 2. Approach to the management of NPPageing; 3. Selection of NPP components important to safety forageing management studies; 4. Methodology for ageing manage-ment studies; 5. Recommendations for ageing management pilotstudies; Appendix I: Examples of ageing related component degra-dation and failure; Appendix II: Ageing degradation mechanismsand susceptible materials and components; Appendix III: Examplesof summary results of ageing management studies from theUSNRC’s Nuclear Plant Ageing Research Programme; AppendixIV: Examples of condition indicator trending as a basis for mitigat-ing component ageing.


NUCLEAR POWER PERFORMANCE AND SAFETY Proceedings Series

Proceedings of a conference, Vienna, 28 September to 2 October1987. These proceedings provide an authoritative and comprehen-sive picture of the current status of and trends in nuclear power,nuclear safety and the nuclear fuel cycle.

Vol. 1: Performance, Overview and Prospects Introduction; Summaries of the Conference; The prospectsfor nuclear power in the 1990s; The need for safety innuclear power programmes; Performance of nuclear powerplants: Outlook for the future; Nuclear power economicsand financing.


Vol. 2: Achievements in Construction and Operation Plant construction achievements; Plant availability achieve-ments; Controlling and financing nuclear power costs;Achievements in technology transfer and infrastructuredevelopment; Advanced systems.


Vol. 3: Safety and International Co-operation The need for safety in nuclear power programmes; Interna-tional co-operation in nuclear safety; Technical aspects inplant safety; Approaches to safety; Panel: Operationalsafety in the 1990s.


Vol. 4: Safety Technology Nuclear safety experience and safety assessment trends;Safety and severe accidents; Safety improvements in designand operation; Poster presentations.


Vol. 5: Nuclear Fuel Cycle Waste management in the 1990s; Decontamination anddecommissioning; Waste management, treatment anddisposal; Nuclear fuel cycle — present and future; Enrich-ment services and advanced reactor fuels; Improvements inreactor fuel utilization and performance; Spent fuelmanagement options: Future needs and economic choices.


Vol. 6: Indexes and Lists Contents of all volumes; List of participants; Author andtransliteration indexes; Index of papers and posters bynumber.


N U S S P R O G R A M M E ( N U C L E A R S A F E T Y S T A N D A R D S )

NUSS is an acronym for Nuclear Safety Standards and comprises aset of publications developed under the IAEA Nuclear Safety Stan-dards programme. NUSS publications are developed for landbasednuclear power plants with thermal neutron reactors. The NUSSprogramme constitutes the first comprehensive non-national set ofpublications on the safety of nuclear power plants.

1. Governmental Organization

CODE ON THE SAFETY OF NUCLEAR POWER PLANTS: GOVERNMENTAL ORGANIZATION Safety Series No. 50-C-G (Rev. 1)

This code recommends the basic requirements for establishing thegovernmental organization responsible for regulating the siting,design, construction, commissioning, operation and decommission-ing of nuclear power plants. This involves the establishment of alegal framework for the regulatory body, defining its role andresponsibilities and those of the applicant/licensee. Further


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requirements are presented with respect to the organization of theregulatory body, its main functions of review and assessment,inspection and enforcement, and the development of regulations andguides.

Contents: Definitions; 1. Introduction; 2. General provisions;3. Role and responsibility of the regulatory body; 4. Organization ofthe regulatory body; 5. Regulations and guides; 6. Licensingprocess; 7. Requirements on the application/licensee; 8. Review andassessment during the licensing process; 9. Licensing decisions;10. Regulatory inspection and enforcement; 11. Emergencypreparedness.

STI/PUB/796 (48 pp., 1 figure; 1988) E ISBN 92–0–123288–8 C ISBN 92–0–523090–1 F ISBN 92–0–223189–3 R ISBN 92–0–423490–3 S ISBN 92–0–323189–7Price: 170 Austrian schillings (€12.35)

QUALIFICATIONS AND TRAINING OF STAFF OF THE REGULATORY BODY FOR NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-G1

This guide recommends how to establish a basic organization forregulating nuclear power and how to develop it into an enlargedorganization that can cope with the regulatory requirements of anexpanding nuclear programme. It emphasizes the qualifications andtraining of the staff needed to regulate nuclear power plants.

Contents: Introduction; General provision; Qualifications of regu-latory personnel; Training of the regulatory staff; Qualifications andutilization of consultants; Qualifications and utilization of advisorycommittees.

STI/PUB/513 (30 pp.; 1979) E out of printC ISBN 92–0–523591–1 F ISBN 92–0–223679–8 R out of print S ISBN 92–0–323080–7 Price: 120 Austrian schillings (€8.72)

INFORMATION TO BE SUBMITTED IN SUPPORT OF LICENSING APPLICATIONS FOR NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-G2

This guide recommends the content and format of the informationthat a regulatory body needs in the course of the licensing process,the channels of communication between the regulatory body and theapplicant/licensee, and the classification of documents and thescheduling of their submission. Other sections deal with the infor-mation related to specific licensing stages, i.e. siting, construction,commissioning, operation and decommissioning.

Contents: 1. Introduction; 2. Information needed during licens-ing process; 3. Classification and format of documents; 4. Schedul-ing of submission.

STI/PUB/515 (44 pp.; 1979) E out of print F ISBN 92–0–223779–4 R out of print S ISBN 92–0–323280–X Price: 150 Austrian schillings (€10.90)

CONDUCT OF REGULATORY REVIEW AND ASSESSMENT DURING THE LICENSING PROCESS FORNUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-G3

This guide discusses the review and assessment process, as well asthe various relationships between the regulatory body and the appli-cant/licensee, the applicant/licensee’s vendor, other governmentalbodies, and consultants and advisory committees. It covers thespecific stages of the licensing process, i.e. siting, construction,commissioning, operation and decommissioning.

Contents: Introduction; Objectives of the review and assessmentprocess; General relationships in the review and assessment process;Exchange of information; Areas for review and assessment; Basesfor review and assessment; Method of review and assessment; Inter-national co-operation in review and assessment.

STI/PUB/571 (49 pp.; 1980) E ISBN 92–0–123480–5 C ISBN 92–0–523488–5 F ISBN 92–0–223980–0 R out of print S ISBN 92–0–323681–3 Price: 170 Austrian schillings (€12.35)

INSPECTION AND ENFORCEMENT BY ➜NEWTHE REGULATORY BODY FOR NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-G4 (Rev. 1)

This revised guide, which supplements Safety Series No. 110: TheSafety of Nuclear Installations, and Safety Series No. 50-C-G(Rev. 1): Code on the Safety of Nuclear Power Plants: Governmen-tal Organization, provides guidance on fulfilling the requirementsfor inspection and enforcement by the regulatory body. It deals withthe responsibilities of the regulatory body, the organization ofinspection programmes, the inspection resources of the regulatorybody, methods of inspection, requirements on the applicant/licenseewith regard to regulatory inspection, inspection reports, and regula-tory action and enforcement.

Contents: Definitions; 1. Introduction; 2. Role of the regulatorybody for inspection and enforcement; 3. Organization of the inspec-tion programme; 4. Inspection resources; 5. Methods of inspection;6. Requirements on the applicant/licensee with regard to regulatoryinspection; 7. Inspection reports; 8. Regulatory action andenforcement.

STI/PUB/1011 (64 pp., 1 figure; 1996)ISBN 92–0–103296–XPrice: 280 Austrian schillings (€20.35)

PREPAREDNESS OF PUBLIC AUTHORITIES FOR EMERGENCIES AT NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-G6

The guide deals with emergency arrangements for which publicauthorities are responsible, the interaction with the operating orga-nization emergency plan and the integration into the overall emer-gency planning. Guidance is given on the main aspects of assigningresponsibility to public authorities, the regulatory body and theoperating organization.

Contents: Introduction; Range of accidents to be considered inemergency planning; Responsibilities for emergency planning, orga-nizing and action; Emergency organization; Emergency planning;


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Emergency assessments and protective measures; Public informa-tion and instruction; Training and exercises; Co-operation acrossboundaries; Annexes.

STI/PUB/601 (46 pp.; 1982)E ISBN 92–0–123082–6C ISBN 92–0–523587–3 F ISBN 92–0–223183–4 R out of print S ISBN 92–0–323183–8 Price: 160 Austrian schillings (€11.63)

LICENCES FOR NUCLEAR POWER PLANTS: CONTENT, FORMAT AND LEGAL CONSIDERATIONS: A Safety GuideSafety Series No. 50-SG-G8

The guide is devoted to the nuclear licence as the principal mecha-nism for linking the legal framework of the regulatory system (i.e.basic legislation plus compulsory regulations) with the responsibili-ties of the principal parties (regulatory body and applicant/licensee)involved in the regulatory system. It describes the principles of thelicensing process, covering the major licensing steps, i.e. siteapproval, authorization of construction, commissioning, operationand decommissioning.

Contents: Introduction; Framework for licenses; Licenses; Autho-rization; Conditions; Annex I: Examples of specific licences in someMember States; Annex II: Examples of the licensing steps in theFederal Republic of Germany for a pressurized-water reactor.

STI/PUB/620 (74 pp.; 1982) E ISBN 92–0–123482–1F ISBN 92–0–223583–X R out of print S ISBN 92–0–323283–4 Price: 210 Austrian schillings (€15.26)

REGULATIONS AND GUIDES FOR NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-G9

The guide provides information, guidance and recommendations toassist a regulatory body in establishing regulations that are compul-sory, and in developing guides that are advisory. The NUSSprogramme, which is based on regulations and guides in MemberStates, is presented as a frame of reference for safety. The systemof regulations and guides required in Member States having anuclear power programme is given, starting with basic legislation.The book covers regulations and guides extensively, citing indus-trial standards and pointing out interrelationships and differencesbetween them.

Contents: Introduction; IAEA NUSS programme; System ofregulations and guides; Programme of regulations and guides;Establishment of regulations; Establishment of guides; Annex 1:Framework of regulatory documents in certain Member States.

STI/PUB/676 (34 pp.; 1984) E ISBN 92–0–123684–0 F ISBN 92–0–223285–7 R out of printS ISBN 92–0–323086–6 Price: 160 Austrian schillings (€11.63)

2. Siting

CODE ON THE SAFETY OF NUCLEAR POWER PLANTS: SITING Safety Series No. 50-C-S (Rev. 1)

This code recommends how to evaluate the site related factors thatare taken into account to ensure that the plant–site combination doesnot constitute an unacceptable risk. After defining the roles of theapplicant and the regulatory body in site selection, evaluation andapproval, general criteria are given for selecting proposed sites andassessing their suitability, for determining site related safety require-ments and for evaluating the acceptability of a site to accommodatea particular nuclear plant.

Contents: Definitions; 1. Introduction; 2. General; 3. Criteria;4. Evaluation of design basis for external events; 5. Sitecharacteristics influencing the effects of the nuclear power plant onthe region.

STI/PUB/797 (36 pp., 1 figure; 1988) E ISBN 92–0–123388–4 C ISBN 92–0–523190–8 F ISBN 92–0–223289–X R ISBN 92–0–423590–X S ISBN 92–0–323289–3 Price: 130 Austrian schillings (€9.45)

EARTHQUAKES AND ASSOClATED TOPICS IN RELATION TO NUCLEAR POWER PLANT SITING: A Safety Guide Safety Series No. 50-SG-S1 (Rev. 1)

This guide puts the main emphasis on determining ground motion asan input to the design of a nuclear power plant and on determiningany potential for surface faulting at a selected site. The type of infor-mation required and the investigations to be performed are describedin the context of their dependence on the geological, seismologicaland geotectonical aspects of the region.

Contents: Definitions; Note on the interpretation of the text;1. Introduction; 2. General requirements; 3. Required informationand investigations (Database); 4. Construction of a regionalseismotectonic model; 5. Evaluation of design basis groundmotions; 6. Potential for surface faulting at the site; 7. Seismicallygenerated water waves; 8. Potential for permanent grounddisplacements associated with earthquakes and geologicalphenomena; Appendix: Seismic intensity scales.

STI/PUB/871 (60 pp.; 1991) E ISBN 92–0–123191–1 F ISBN 92–0–200194–4R ISBN 92–0–400194–1 S ISBN 92–0–300294–4Price: 240 Austrian schillings (€17.44)

SEISMIC ANALYSIS AND TESTING OF NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-S2

Superseded. Revised version published as Safety SeriesNo. 50-SG-D15, Seismic Design and Qualification for NuclearPower Plants, see under 3. Design.


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ATMOSPHERIC DISPERSION IN NUCLEAR POWER PLANT SITING: A Safety Guide Safety Series No. 50-SG-S3

The guide addresses the meteorological investigations needed atdifferent stages in a site survey, in site evaluation and in assessingoff-site consequences of operational states and accident conditions.It covers meteorological phenomena and mechanisms involved inthe dispersion of radioactive effluents, calculation methods forconcentration and deposition, input data needed for calculations,meteorological instrumentation requirements, data analysis systemrequirements and other related topics.

Contents: Introduction; On-site and off-site meteorological investi-gation programme; Atmospheric dispersion models; Averageshort-term concentration estimates; Meteorological aspects of emer-gency planning at nuclear power plants; Annex I: Turbulence andatmospheric dispersion; Annex II: Atmospheric stability; Annex III:Equivalent height of plume Dh (non-buoyant plume); Annex IV:Examples of simplified models; Annex V: A direct method fordetermining stability class (Pasquill method and modifications);Annex VI: Dependence of concentration on sampling time;Annex VII: Modified Bulk Richardson number method for sy andsz; Annex VIII: Additional graphs for sy and sz.

STI/PUB/549 (107 pp., 16 figures; 1980) E ISBN 92–0–623180–4 C ISBN 92–0–523886–4 F out of print R out of print S ISBN 92–0–323382–2 Price: 250 Austrian schillings (€18.17)

SITE SELECTION AND EVALUATION FOR NUCLEAR POWER PLANTS WITH RESPECT TO POPULATION DISTRIBUTION: A Safety Guide Safety Series No. 50-SG-S4

This guide presents population distribution data requirements,examples of territory screening and various approaches to evaluatingpopulation distribution and site selection. It also gives an overviewof radiological impact assessment with respect to population data(current and projected), data format (concentric rings and sectors)and supplementary site information.

Contents: Introduction; Data requirements; Territory screening andpreliminary site selection methods; Radiological impact and finalsite evaluation; Annex I: Histograms of population distributionaround some nuclear power plant sites; Annex II: Details of methodsdescribed in Section 3; Annex III: Suggested bases for choice ofmethod.

STI/PUB/569 (51 pp., 6 figures; 1980) E ISBN 92–0–123580–1 C ISBN 92–0–523188–6 F ISBN 92–0–223680–1 R out of print S ISBN 92–0–323381–4 Price: 170 Austrian schillings (€12.35)

EXTERNAL MAN-INDUCED EVENTS IN RELATION TO NUCLEAR POWER PLANT SITING: A Safety Guide Safety Series No. 50-SG-S5

This guide discusses the hazardous phenomena associated withexternal man-induced events, such as aircraft crashes, explosions,release of hazardous fluids using screening distances and probabili-ties. Their potential effects on the nuclear power plant and methods

used to develop adequate design bases for the plant to prevent sucheffects are also included.

Contents: Introduction; Potential sources of man-induced eventsand associated features; Collection of information and evaluation;Administrative aspects; Preliminary screening and detailed evalua-tions; Aircraft crashes; Explosions; Release of hazardous fluids;Other man-induced events; Annex I: Aircraft crashes; Annex II:Chemical explosions; Annex III: Hazards from drifting clouds;Annex IV: Fire.

STI/PUB/585 (62 pp.; 1981) E ISBN 92–0–123081–8 C ISBN 92–0–523590–3 F ISBN 92–0–723081–X R out of print S ISBN 92–0–323282–6 Price: 190 Austrian schillings (€13.81)

HYDROLOGICAL DISPERSION OF RADIOACTIVE MATERIAL IN RELATION TO NUCLEAR POWER PLANT SITING: A Safety GuideSafety Series No. 50-SG-S6

This guide deals with the dispersion of normal and accidentalreleases of radioactive material from nuclear power plants intosurface water for a full range of releases, including steady state(routine releases), instantaneous or puff (accidental releases), andtime dependent long term releases (routine or accidental releases). Itdescribes the information needed, gives recommendations onmeasurement programmes and the selection and use of appropriatemathematical models for evaluating dispersion.

Contents: Introduction; Information needed at the site survey stage;Information needed at the site evaluation stage; Modelling ofradionuclide dispersion in surface waters; Appendix A: Generaldiscussion of radionuclide dispersion modelling in surface waters;Appendix B: Models for the initial dilution of radioactive material;Appendix C: Models for far-field radionuclide dispersion in rivers;Appendix D: Models for far-field radionuclide dispersion from opencoasts; Appendix E: Models for dispersion of radionuclides in estu-aries; Appendix F: Models for far-field radionuclide dispersion inimpoundments; Annex I: Measurement of diffusion coefficients;Annex II: Measurement of equilibrium sediment distribution coeffi-cients; Annex III: Examples of accuracy and sensitivity of instru-mentation; Annex IV: Equations of simple models for radionuclidedispersion in rivers, open coasts, estuaries and impoundments;Annex V: Advanced models for radionuclide dispersion in rivers;Annex VI: Advanced models for radionuclide dispersion in the nearshore of open coastal areas; Annex VII: Advanced models for radio-nuclide dispersion in estuaries; Annex VIII: Advanced models forradionuclide dispersion in impoundments; Annex IX: Depositedairborne radioactive material as a source for dispersion in surfacewaters.

STI/PUB/539 (116 pp., 14 figures; 1985) E ISBN 92–0–123285–3 F ISBN 92–0–223889–8 R ISBN 92–0–423587–X S ISBN 92–0–323187–0 Price: 360 Austrian schillings (€26.16)

NUCLEAR POWER PLANT SITING: HYDROGEOLOGICAL ASPECTS: A Safety Guide Safety Series No. 50-SG-S7

This guide deals with the determination of the radionuclideconcentration in groundwater resulting from postulated releasesfrom nuclear power plants. The main emphasis is on the behaviourof radioactive material in groundwater and on the methods for


36

assessing the radionuclide movement in various aquifers. Thismovement of radionuclides in the ground is essentially controlled bythe phenomena of transport (bulk motion of groundwater), hydrody-namic dispersion (spread of contaminate front) and ion exchange.

Contents: Introduction; Site survey stage; Site evaluation stage;Modelling of radionuclide dispersion and retention in groundwater;Groundwater monitoring programme; Appendix A: Modelling ofradionuclide movement in groundwater; Annex I: Considerationsrelated to groundwater availability; Annex II: Analytical solutions ofthe advective transport and hydrodynamic dispersion equations;Annex III: Accuracy and reliability of measurements in hydrogeol-ogy; Annex IV: Examples of methods and frequencies of measure-ments within the monitoring programme; Special definitions.

STI/PUB/677 (76 pp.; 1984) E ISBN 92–0–623284–3 F ISBN 92–0–223286–5 R ISBN 92–0–423486–5 S ISBN 92–0–323586–8Price: 250 Austrian schillings (€18.17)

SAFETY ASPECTS OF FOUNDATIONS OF NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-S8

Foundations are the link between plant structures and subsoil. Infor-mation on the geology and subsurface characteristics of the site is aninput for the design. Without proper adaptation of the design to thesubsurface situation, safety may be impaired. This guide addressesthe mechanical characteristics of different subsurface materials.

Contents: Introduction; Design profiles; Methods of analysis;Discussion of relevant aspects; Programme of investigation; Prelim-inary foundation work; Monitoring of geotechnical parameters;Quality assurance requirements for programmes of investigation;Appendix A: Site investigation programmes; Appendix B: Subsur-face investigation techniques; Appendix C: Laboratory testingmethods; Appendix D: Foundation soil improvement techniques;Appendix E: Geotechnical instrumentation.

STI/PUB/727 (70 pp., 1 figure; 1986) E ISBN 92–0–124186–0 F ISBN 92–0–223090–0 R ISBN 92–0–423390–7 S ISBN 92–0–324288–0 Price: 260 Austrian schillings (€18.89)

SITE SURVEY FOR NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-S9

This guide describes the first stage of the siting process for nuclearpower plants, the site survey, which involves the study and investi-gation of a large region to select one or more preferred candidatesites. It deals only with the safety aspects in the site survey, althoughit is recognized that the review of the safety aspects of sites takesplace in a larger context, including questions related to feasibility.

Contents: Introduction; Site survey process; Organization of a sitesurvey; Specific safety-related site characteristics; Documentation;Annex I: Elements of site survey methodology; Annex II: Screeningand ranking of areas and sites; Annex III: Non-safety considerations.

STI/PUB/682 (48 pp., 2 figures; 1984) E ISBN 92–0–123884–3 F ISBN 92–0–223086–2 R ISBN 92–0–423685–X S ISBN 92–0–323285–0 Price: 190 Austrian schillings (€13.81)

DESIGN BASIS FLOOD FOR NUCLEAR POWER PLANTS ON RIVER SITES: A Safety Guide Safety Series No. 50-SG-S10A

This guide presents techniques for determining the design basisflood (DBF) to be used for siting nuclear power plants at or nearnon-tidal reaches of rivers and for the protection of nuclear powerplants against floods. Both natural floods and those due to dam fail-ures are discussed. Flooding could have repercussions on safety;consequently the DBF has to be chosen to have a very low proba-bility of exceedance per annum. Two types of methods (probabilis-tic and deterministic) are discussed.

Contents: Introduction; Preliminary investigation; Detailedinformation; Methodologies for flood analysis; Floods due toprecipitation; Floods from sudden releases of natural or artificialstorage; Floods from causes other than precipitation and releasefrom storage; Relationship between flow, water level and other floodparameters; Initial conditions and combined events; Flood protec-tion aspects of nuclear power plant siting; Monitoring and forecast-ing for plant protection; Changes in flood characteristics of drainagebasins; Annex I: Frequency curve method and its relation to stochas-tic methods; Annex II: Stochastic methods in evaluating runofffloods; Annex III: Causes of floods other than precipitation andrelease from storage; Annex IV: Monitoring and forecasting forplant protection.

STI/PUB/602 (64 pp.; 1983) E ISBN 92–0–123083–4 F ISBN 92–0–223384–5 R ISBN 92–0–423484–9 S ISBN 92–0–323484–5 Price: 220 Austrian schillings (€15.99)

DESIGN BASIS FLOOD FOR NUCLEAR POWER PLANTS ON COASTAL SITES: A Safety Guide Safety Series No. 50-SG-S10B

Sites vulnerable to coastal flooding are located on open coastalregions directly exposed to or having a shore on a major body ofwater, semi-enclosed bodies of water such as lagoons, estuaries,rivers, fjords and rias, or enclosed bodies of water such as lakes andreservoirs. Floods due to waves, surges, seiches and tsunamis arediscussed, including ways to combine the effects of these to calcu-late design values for run-up and draw-down.

Contents: Introduction; Preliminary investigation; Detailed infor-mation; Flooding by storm surges and seiches; Tsunami flooding;Wave effects; Reference water level; Ice effects; Combined floodingevents; Design basis for the flood; Shoreline stability; Flood protec-tion aspects of nuclear power plant siting; Monitoring and warningfor plant protection; Appendix A: Stochastic methodologies in surgeanalysis; Annex I: Probable maximum storm characteristics andstorm surge analysis; Annex II: Frequency distribution functions;Annex III: Tsunami evaluation; Annex IV: Nearshore wave effects;Annex V: Example of possible combinations of flood-causingevents; Annex VI: Monitoring and warning systems.

STI/PUB/655 (92 pp., 7 figures; 1983) E ISBN 92–0–123983–1 F ISBN 92–0–223884–7 R ISBN 92–0–423085–1 S ISBN 92–0–323784–4 Price: 300 Austrian schillings (€21.80)


37

EXTREME METEOROLOGICAL EVENTS IN NUCLEAR POWER PLANT SITING, EXCLUDING TROPICAL CYCLONES: A Safety Guide Safety Series No. 50-SG-S11A

This guide provides methods for determining extreme values ofmeteorological variables such as wind speed and temperature, andfor determining the design basis events for specific meteorologicalphenomena such as tornadoes. Secondary effects of tornadoes, e.g.tornado-borne missiles, are also discussed as part of the designbasis.

Contents: Introduction; General methods; Extreme meteorologicalvariables; Meteorological aspects of the design basis of the ultimateheat sink and its associated systems; Extreme meteorologicalphenomena; Meteorological aspects of the probable maximumflood; Annex I: Statistics of extremes; Annex II: Normalization ofmaximum wind speed data to allow for averaging period, referenceheights and terrain characteristics; Annex III: Precipitation adjust-ment from fixed interval data; Annex IV: Screening of meteorologi-cal information, and its use for cooling pond (ulitmate heat sink)evaluation; Annex V: Heat transfer and evaporation calculations fora cooling reservoir associated with the ultimate heat sink; Annex VI:Tornadoes.

STI/PUB/614 (76 pp.; 1981)E ISBN 92–0–123981–5 F ISBN 92–0–223083–8 R out of printS ISBN 92–0–823282–4 Price: 220 Austrian schillings (€15.99)

DESIGN BASIS TROPICAL CYCLONE FOR NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-S11B

This guide describes first the general characteristics of tropicalcyclones with particular emphasis on their pressure and wind struc-tures. The collection of information, the data sources and require-ments are treated in some detail. The subsequent sections deal witha description of the procedures available for evaluating the probablemaximum tropical cyclone (PMTC), including deterministic andprobabilistic approaches for determining the pressure at the eye of atropical cyclone.

Contents: Introduction; Collection of information; Procedures forevaluating the PMTC; Evaluation of other parameters needed todefine the PMTC wind field; Determination of the PMTC windfield; Annex I: Tropical cyclone nomenclature; Annex II: Back-ground for the development of the deterministic method; Annex III:Deterministic approach to p0; Annex IV: Examples of estimating p0for the South China Sea region by the probabilistic method; AnnexV: p0 relations with heights of pressure levels; Annex VI: Examplefor evaluation of limits for miminum R for the Probable MaximumHurricane (PMH) for the tropical North Atlantic (abstract fromSchwerdt et al.); Annex VII: Derivation of equations for computingthe maximum gradient wind speed.


3. Design

CODE ON THE SAFETY OF NUCLEAR POWER PLANTS: DESIGN Safety Series No. 50-C-D (Rev. 1)

This code establishes the general safety approach in design, sets outthe basic requirements to ensure the necessary system reliability anddefines the mandatory safety features of a nuclear power plant utiliz-ing thermal neutron reactors. The basic nuclear safety requirementsfor structures, systems and components compiled in this code areenlarged in the associated safety guides.

Contents: Definitions; 1. Introduction; 2. Safety philosophy;3. General design criteria; 4. Reactor core; 5. Reactor coolantsystem; 6. Information and control facilities; 7. Protection sys-tem; 8. Emergency power supply; 9. Containment system; 10. Radi-ation protection; 11. Fuel handling and storage systems; 12. Designconfirmation; Appendix: Postulated Initiating Events (PlEs).

STI/PUB/798 (58 pp., 1 figure; 1988) E ISBN 92–0–123488–0 C ISBN 92–0–523290–4 F ISBN 92–0–223389–6 R out of print S ISBN 92–0–323389–X Price: 190 Austrian schillings (€13.81)

SAFETY FUNCTIONS AND COMPONENT CLASSIFICATION FOR BWR, PWR, AND PTR: A Safety GuideSafety Series No. 50-SG-D1

This guide recommends how to classify structures, systems andcomponents according to their importance to safety. The classifica-tion is translated into graded safety requirements that in turn influ-ence the design. Twenty safety functions are listed and the method-ology outlined ranks them according to their importance to safety.

Contents: Introduction; Safety functions; Ranking of safety func-tions; Assignment of safety class requirements; Appendix A: Designrequirements for structural integrity of boundaries of fluid-retainingcomponents.

STI/PUB/542 (68 pp.; 1979) E out of print C ISBN 92–0–524086–7 F ISBN 92–0–223580–5 R out of printS ISBN 92–0–323380–6 Price: 170 Austrian schillings (€12.35)

FIRE PROTECTION IN NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-D2 (Rev. 1)

This guide points out the necessity of measures for protecting plantitems which are important to safety against fires of internal andexternal origin. Fire, being a real threat to nuclear safety, shouldreceive adequate attention from the beginning of the design processthroughout the life of a plant. The present guide was developed toenlarge on the general requirements given in the Code on the Safetyof Nuclear Power Plants: Design, Safety Series No. 50-SG-D(Rev. 1), published in 1988.

Contents: Definitions; 1. Introduction; 2. General fire protectionrequirements; 3. Fire protection design approach; 4. Fire prevention;5. Fire detection and extinguishing; 6. Mitigation of secondary fire


38

effects; 7. Quality assurance; 8. Operational aspects of manual firefighting; Appendix I: Halon fire extinguishing systems; Appendix II:Escape routes; Annex I: Additional guidance on the preparation offire hazards analyses; Annex II: Fire barriers; Annex III: List ofcontrols; Annex IV: Fire detection systems; Annex V: Automaticsprinkler and water spray systems; Annex VI: Example of possiblelayout of fire water supply system; Annex VII: Schematic examplesof compartment separation for ventilation; Annex VIII: Electricalcable insulation.

STI/PUB/897 (93 pp., 4 figures; 1992) E ISBN 92–0–101892–4 F ISBN 92–0–202087–3R ISBN 92–0–401498–9 S ISBN 92–0–302398–4 Price: 320 Austrian schillings (€23.26)

PROTECTION SYSTEMS AND RELATED FEATURES IN NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-D3

This guide gives design guidance on requirements for the protectionsystem which monitors the relevant plant variables and performs —in conjunction with the safety actuation systems and safety systemsupport features — all safety tasks that may become necessary whenunacceptable.

Contents: Introduction; Extent of the protection system; Generaldesign principles; Safety system monitoring; Safety actuationsystems and safety system support features; Design verifica-tion; System documentation; Annex I: Information on certaindefinitions.

STI/PUB/551 (55 pp., 4 figures; 1980) E ISBN 92–0–623280–0 C ISBN 92–0–523588–1 F ISBN 92–0–223681–X R out of printS ISBN 92–0–323781–X Price: 150 Austrian schillings (€10.90)

PROTECTION AGAINST INTERNALLY GENERATED MISSILES AND THEIR SECONDARY EFFECTS IN NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-D4

This guide covers the protection of nuclear power plants againstmissiles that may result from failures of equipment. Missiles fromsources outside the plant are not addressed. The recommendationsgiven are intended as an aid in assessing design adequacy. Overallaspects of what constitutes adequate protection are thus more exten-sively elaborated than the details of how to accomplish that task.

Contents: Introduction; General philosophy; Origin of missiles andappropriate design considerations; Secondary effects; Protectivemethods and means against missiles; Documentation requirements;Annex.

STI/PUB/552 (44 pp., 3 figures; 1980) E ISBN 92–0–123880–0 C ISBN 92–0–523087–1 F ISBN 92–0–223780–8 R out of printS ISBN 92–0–823181–X Price: 150 Austrian schillings (€10.90)

EXTERNAL MAN-INDUCED EVENTS IN ➜NEWRELATION TO NUCLEAR POWER PLANTDESIGN: A Safety Guide Safety Series No. 50-SG-D5 (Rev. 1)

This guide advises on the protection of nuclear power plants againstthe effects of external man-induced events which originate outsidethe site and which have been identified and selected as design basisexternal man-induced events (DBEMIEs) according to Safety GuideNo. 50-SG-S5, to which this guide is complementary.

Contents: Definitions; 1. Introduction; 2. General design philo-sophy; 3. Aircraft crashes; 4. Fires due to man-induced events;5. Explosions; 6. Hazards from drifting clouds; 7. Corrosive fluidreleases; 8. Ship collision; Annex I: Aircraft crashes; Annex II: Gascloud explosions.

STI/PUB/984 (70 pp., 9 figures; 1996) E ISBN 92–0–103295–1 F ISBN 92–0–202297–6R ISBN 92–0–401797–XS ISBN 92–0–300499–8Price: 280 Austrian schillings (€20.35)

ULTIMATE HEAT SINK AND DIRECTLY ASSOCIATED HEAT TRANSPORT SYSTEMS FOR NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-D6

The ultimate heat sink and its directly associated heat transportsystems addressed in this guide are required to remove residual heatfrom the core after reactor shutdown, and during and after appropri-ate operational states and accident conditions. The guide coversdesign considerations for various types of ultimate heat sinks andthe directly associated heat transport systems, and for various typesand sources of related heat transport fluids.

Contents: Introduction; Design principles; Postulated initiatingevents; Design features; Annex I: Typical configurations of an ulti-mate heat sink and its directly associated heat transport systems;Annex II: Typical events to be considered for credible combinationsin establishing postulated initiating events for design of UHS.

STI/PUB/581 (62 pp., 8 figures; 1981) E ISBN 92–0–123581–X C ISBN 92–0–523287–4 F ISBN 92–0–223482–5R out of printS ISBN 92–0–823382–0 Price: 180 Austrian schillings (€13.08)

EMERGENCY POWER SYSTEMS AT NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-D7 (Rev. 1)

The safety objective, and basic and detailed requirements for thefulfillment of its safety function, are presented for the various typesof emergency power systems. AC, DC, non-interruptible AC,standby diesel generators and non-electric systems such as steamturbines for individual pumps and instrument air, and the necessarydistribution systems are dealt with. Some guidance is also given forthe main and auxiliary outside grid connections.

Contents: Definitions; 1. Introduction; 2. Power supplies;3. General design principles; 4. General design requirements;5. Detailed design requirements; 6. Design for surveillance, testingand maintenance; 7. Design confirmation; Annex I: Examples oftests, test intervals and monitoring displays; Annex II: Examples of


39

electrical power supplies for a nuclear power plant with a singlereactor.

STI/PUB/870 (73 pp., 9 figures; 1991) E ISBN 92–0–123291–8 F ISBN 92–0–200493–5 R ISBN 92–0–400193–3S ISBN 92–0–300193–XPrice: 280 Austrian schillings (€20.35)

SAFETY RELATED INSTRUMENTATION AND CONTROL SYSTEMS FOR NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-D8

This guide deals primarily with design requirements for instrumen-tation and control systems important to safety but not part of theprotection system (Safety Series No. 50-SG-D3). It givesrecommendations on instrumentation and control systems for theprevention or termination of plant transients to avoid, if possible, theactuation of safety systems.

Contents: Introduction; Extent of the l&C systems; Design basis;Design requirements; Documentation; Appendix: Single failurecriterion for safety-related l&C systems.

STI/PUB/678 (48 pp., 1 figure; 1984) E ISBN 92–0–623184–7 F ISBN 92–0–223085–4 R ISBN 92–0–423485–7 S ISBN 92–0–323585–XPrice: 190 Austrian schillings (€13.81)

DESIGN ASPECTS OF RADIATION PROTECTION FOR NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-D9

This guide provides principles and practical details on the provisionsto be made in the design of nuclear power plants to protect sitepersonnel and the general public from ionizing radiation duringoperational states and accident conditions. The dose limitationsystems, including the ALARA principle, are described as the basisfor appropriately addressing the radiation protection features innuclear power plant design.

Contents: Introduction; Basic concepts of radiation protection;Radiation protection aspects in design; Sources of radiation duringnormal operation; Sources of radiation under accident conditions;Protection of site personnel during operational states; Protection ofsite personnel under accident conditions; Protection of the publicunder accident conditions; Guidelines for determining radiationdose rates during operational states; Considerations for determiningpotential doses under accident conditions; Monitoring of radiationduring operational states; Monitoring of radiation under accidentconditions; Process monitoring for radiological protection; Auxil-iary facilities; Annex I. Radioactive releases and exposure limits formembers of the public; Annex II. Depressurization accidents inAGR reactors; Annex III. Zoning of nuclear power plants; Annex IV.Methodology for source and flux calculations; Annex V. Statementon the role of quantitative optimization in nuclear power plant radi-ation protection.

STI/PUB/687 (102 pp., 1 figure; 1985) E ISBN 92–0–123585–2 C ISBN 92–0–523291–2 F ISBN 92–0–223387–X R ISBN 92–0–423188–2 S ISBN 92–0–323686–4Price: 310 Austrian schillings (€22.53)

FUEL HANDLING AND STORAGE SYSTEMS IN NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-D10

This guide gives the safety requirements for the activities related tothe receipt of fuel at the plant, its inspection and storage before use,the transfer of unirradiated fuel into the reactor, the removal of irra-diated fuel and fuel shuttling operations, the storage inspection andpreparation of irradiated fuel for shipment off-site, and the handlingof transport casks. It covers both on-load and off-load refuellingfeatures and different storage facilities.

Contents: Introduction; General design and safety principles;Handling and storage of unirradiated fuel; Handling and storage ofirradiated fuel and other core components; Handling and transport ofshipping casks; Multireactor considerations; Performance require-ments; Quality assurance and documentation; Annex 1: Typical flowcharts for fuel handling and storage systems.


GENERAL DESIGN SAFETY PRINCIPLES FOR NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-D11

The basic safety approach of defence in depth and high functionalsystem availability is addressed in this guide. Attention is also paidto the safety implications of operator actions and their considerationin the design.

Contents: Introduction; Scope; Safety principles; Safety approach;Design requirements; Safety analysis; Equipment qualification;Quality assurance; Appendix A: Postulated initiating events (PIEs);Annex I: Safety principles used in the development of NUSS docu-ments; Annex II: Typical listings for the compilation of postulatedinitiating events; Annex III: List of safety functions from IAEASafety Series No. 50-SG-D1.


DESIGN OF THE REACTOR CONTAINMENT SYSTEMS IN NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-D12

Safety requirements for the design of containment systems arepresented in a generic form. The various functions of confinement,isolation, energy management, radionuclide management andcombustible gas control as well as the structural and leak integrityare covered. Annexes provide examples for the most common designsolutions and other aspects.

Contents: Introduction; General design considerations; Designbasis for the containment system; Design requirements; Tests andinspection; Quality assurance and documentation; Annex I: Exam-ples of containment system design concepts; Annex II: Containmentmonitoring instrumentation for early detection of developing


40

deviations from normal operation in light water reactors; Annex III:Illustration of categories of isolation features.

STI/PUB/693 (68 pp., 8 figures; 1985)E ISBN 92–0–123785–5 F ISBN 92–0–223287–3 R ISBN 92–0–423687–6 S ISBN 92–0–323886–7 Price: 240 Austrian schillings (€17.44)

REACTOR COOLANT AND ASSOCIATED SYSTEMS IN NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-D13

This guide covers the safety design considerations for variousreactor coolant and associated systems for operational states andaccident conditions including the selection, sizing and reliabilityaspects. This includes safety systems such as emergency corecooling, residual heat removal or emergency feedwater systems. Thedetailed design of particular components, e.g. heat exchangers,pumps and vessels, is not covered.

Contents: Introduction; Extent of the reactor coolant and associatedsystems; General design principles; Detailed design principles;Quality assurance; Annex I: Reactor coolant and associated systemsdiagrams; Annex II: Main reactor coolant system components;Annex III: Listing of pressure boundary codes and standards used insome Member States.

STI/PUB/731 (70 pp., 6 figures; 1986) E ISBN 92–0–123886–X F ISBN 92–0–223887–1 R ISBN 92–0–423789–9 S ISBN 92–0–323587–6 Price: 260 Austrian schillings (€18.89)

DESIGN FOR REACTOR CORE SAFETY IN NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-D14

This guide covers the mechanical, chemical, thermal, hydraulic,neutronic and irradiation considerations important to the safe designof a nuclear reactor core. The core features of commonly usedreactor types including light and heavy water reactors, as well as gascooled reactors, are addressed.

Contents: Introduction; Safety design principles; Core designrequirements; Qualification and testing; Quality assurance in design,manufacture and operation; Annex I: Reactivity coefficients; AnnexII: Pellet-cladding interaction; Annex III: Design considerations forcore management; Annex IV: Examples of postulated initiatingevents which can influence the core design.


SEISMIC DESIGN AND QUALIFICATION FOR NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-D15

This guide was originally issued as Safety Guide No. 50-SG-S2. Itprovides details on the design of a nuclear power plant such thatearthquakes at the site determined according to Safety Guide No.50-SG-S1 will not jeopardize its safety. It gives guidance onmethods and procedures for analysing, testing and qualifying

structures and equipment such that they fulfil the purpose foreseenin the design.

Contents: Definitions; 1. Introduction; 2. General concept;3. Seismic design; 4. Seismic qualification: Analysis, testing, earth-quake experience and indirect methods; 5. Seismic instrumentation;Appendix I: Methods of seismic analysis; Appendix II: Modellingtechniques; Annex I: Examples of lists of seismic category I andother category items; Annex II: Sloshing and impulse effects inliquid containers.

STI/PUB/917 (77 pp., 4 figures; 1992) E ISBN 92–0–103592–6 F ISBN 92–0–201997–5R ISBN 92–0–401798–8Price: 280 Austrian schillings (€20.35)

4. Operation

CODE ON THE SAFETY OF NUCLEAR POWER PLANTS: OPERATION Safety Series No. 50-C-O (Rev. 1)

This code is prepared for those responsible for operating and regu-lating stationary nuclear power plants. Its safety requirements andrecommendations cover surveillance, operational limits and condi-tions, commissioning, plant management and site personnel, operat-ing instructions and procedures, maintenance, testing, examinationand inspection, modifications, radiological protection, effluent andwaste management, emergency arrangements, quality assurance,security, records and reports, and decommissioning.

Contents: Definitions; 1. Introduction; 2. Surveillance by theoperating organization and by the regulatory body; 3.Operationallimits and conditions; 4. Commissioning; 5. Structure of theoperating organization; 6. Plant management and operatingpersonnel; 7. Operating instructions and procedures; 8. Mainte-nance, testing, examination and inspection; 9. Core managementand fuel handling; 10. Modifications; 11. Radiation protection;12. Effluent and waste management; 13. Emergency preparedness;14. Quality assurance programme; 15. Security; 16. Review of oper-ation and feedback of experience; 17. Records and reports;18. Decommissioning.

STI/PUB/799 (42 pp., 1 figure; 1988) E ISBN 92–0–123588–7 C ISBN 92–0–523390–0 F ISBN 92–0–223489–2 R ISBN 92–0–423790–2 S ISBN 92–0–323489–6 Price: 160 Austrian schillings (€11.63)

STAFFING OF NUCLEAR POWER PLANTS AND THE RECRUITMENT, TRAINING AND AUTHORIZATION OFOPERATING PERSONNEL: A Safety Guide Safety Series No. 50-SG-O1 (Rev. 1)

This guide outlines the factors to be considered to ensure that theoperating organization has a sufficient number of qualified sitepersonnel who are aware of their duties and responsibilities. Itcovers the organization for the nuclear power plant, the educationalqualifications and experience of the persons recruited, the recruit-ment and training schedule, the training of operating personnel, theauthorization of persons whose duties have an immediate bearing onsafety, and re-training of personnel.


41

Contents: Definitions; 1. Introduction; 2. Organizational plan;3. Recruitment; 4. Training and qualification; 5. Authorization;6. Records; Annex: Nuclear power plant organizational charts.

STI/PUB/874 (59 pp., 5 figures; 1991) E ISBN 92–0–123391–4 F ISBN 92–0–203195–9R ISBN 92–0–405095–0 S ISBN 92–0–302095–0 Price: 240 Austrian schillings (€17.44)

IN-SERVICE INSPECTION FOR NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-O2

This guide outlines provisions for the preparation of in-serviceinspection programmes for critical systems and components ofprimary reactor coolant systems. Recommendations cover methodsand techniques applicable to in-service inspection and the minimumfrequency of examinations and tests. Methods of evaluating theresults are described and acceptance standards defined. Methods ofpreparing the necessary documentation, procedures and records arerecommended.

Contents: Introduction; Design considerations; In-service examina-tion; Evaluation of examination results; Test requirements; Repairand replacement; Equipment, methods and techniques; Administra-tive aspects; Records; Annex I: In-service inspection oflight-water-cooled reactor plants; Annex II: In-service inspection ofheavy-water-cooled pressure-tube reactor plants; Annex III:In-service inspection of gas-cooled reactor plants with pressurevessels.

STI/PUB/554 (47 pp.; 1980) E out of print C ISBN 92–0–523387–0 F ISBN 92–0–223880–4 R out of print S ISBN 92–0–823081–3Price: 160 Austrian schillings (€11.63)

OPERATIONAL LIMITS AND CONDITIONS FOR NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-O3

The concept of operational limits and conditions for the safe opera-tion of nuclear power plants is presented. An essential element of theconcept is the distinction between safety limits established to retainthe integrity of fuel cladding and pressure boundary barriers, thesettings of safety systems provided to prevent safety limits frombeing exceeded or to initiate operation of engineered safety systems,and limits and conditions for normal operation established toprovide acceptable margins for operation.

Contents: 1. Introduction; 2. Concept of operational limitsand conditions; 3. Contents of operational limits andconditions; 4. Responsibilities of the operating organization;5. Documentation.

STI/PUB/531 (35 pp.; 1979) E ISBN 92–0–123479–1C ISBN 92–0–524286–1 F ISBN 92–0–223879–0 R out of print S ISBN 92–0–323082–3 Price: 140 Austrian schillings (€10.17)

COMMISSIONING PROCEDURES FOR NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-O4

This guide deals with the commissioning of all types of nuclearpower plants with thermal neutron reactors. Its purpose is to giveguidance on good practice, the implementation of which will enablecommissioning to proceed safely and provide assurances that theplant has been constructed and can operate according to designintent. The guide covers the programme of tests to be prepared andthe responsibility for implementing and reporting on the variousparts of the commissioning programme.

Contents: Introduction; Commissioning programme; Principalstages of commissioning; Testing procedures; Organization, respon-sibilities and audit; Interfaces between construction, commissioningand operating activities at the site; Deviations during commission-ing; Documentation; Appendix A: Fuel loading; Annex I: Detailedlist of commissioning tests; Definitions.

STI/PUB/574 (58 pp.; 1980)E out of printC ISBN 92–0–523187–8 F ISBN 92–0–223981–9 R ISBN 92–0–323881–6 S ISBN 92–0–423282–XPrice: 180 Austrian schillings (€13.08)

RADIATION PROTECTION DURING OPERATION OF NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-O5

This guide deals with the protection of site personnel and generalpublic from the effects of ionizing radiation. It outlines how radia-tion protection on-site for all operational states of the plant, accidentconditions and emergency situations can be implemented. Amongthe organizational aspects dealt with are the duties and responsibili-ties of the operating organization, the plant management and thehealth physics group.

Contents: Introduction; Basic principles of radiation protection;Organizational aspects; Practical aspects of implementation of aradiation protection programme; Effluent release, radioactive wastedisposal and environmental monitoring; Storage, handling andtransport of radioactive materials; Training; Facilities and equip-ment; Records; Annex I: Explanatory notes on radiation protectionterms and concepts used in this Guide; Annex II: Some specificlimits and requirements summarized from publications of the ICRP.

STI/PUB/654 (54 pp.; 1983)E ISBN 92–0–123783–9 C ISBN 92–0–523088–X F ISBN 92–0–223784–0 R ISBN 92–0–423285–4 S ISBN 92–0–323284–2Price: 200 Austrian schillings (€14.53)

PREPAREDNESS OF THE OPERATING ORGANIZATION(LICENSEE) FOR EMERGENCIES AT NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-O6

This guide outlines, for accidents at nuclear power plants, the prin-cipal elements in devising and implementing emergency plans sothat actions in conjunction with national, regional and local govern-ment and other organizations ensure an orderly and timely decisionmaking process and availability of essential personnel, equipment,supplies and services to limit the consequences of the emergency onthe public.


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Contents: Introduction; Basis and content of the operatingorganization emergency plan; Emergency conditions; Organizationfor emergencies; Emergency facilities; Emergency measures; Aid toaffected personnel; Termination of emergency; Maintainingemergency preparedness; Records; Annex I: Emergency plan imple-menting procedures; Annex II: Example of functional emergencyorganization on site; Annex III: Example of types of emergencyequipment in the control room; Annex IV: Example of EmergencyControl Centre equipment; Annex V: Example of types of emer-gency equipment stored on site; Annex VI: Example of logicdiagram of site emergency arrangements; Annex VII: Use of stableiodine tablets for thyroid protection; Annex VIII: Example of typesof emergency medical supplies available at the plant; Annex IX:Emergency kit and ambulance supplies; Annex X: Contaminationcontrol in transportation of casualties.

STI/PUB/618 (76 pp.; 1982) E out of printC ISBN 92–0–523691–8 F ISBN 92–0–223184–2 R out of print S ISBN 92–0–823482–7 Price: 190 Austrian schillings (€13.81)

MAINTENANCE OF NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-O7 (Rev. 1)

The guide covers the organizational and procedural aspects of effec-tive maintenance for safe operation of nuclear power plants, but doesnot provide detailed technical advice on the maintenance of particu-lar items. It gives guidance on preventive and remedial measuresnecessary to ensure safety. Experience from OSART missions andfrom the use of the Manual on Maintenance of Systems and Compo-nents Important to Safety was used for the revision. The sections onthe maintenance programme, administrative control and modifica-tions have been revised and a new section on the feedback of expe-rience has been developed.

Contents: Definitions; Note on the interpretation of the text;1. Introduction; 2. Maintenance programme; 3. Organization andresponsibilities for maintenance; 4. Administrative controls;5. Maintenance facilities; 6. Replacements and repairs; 7. Modi-fications; 8. Stores; 9. Feedback of experience; 10. Records; Surveil-lance, review and audit programme; Annex: Administrative aspectsof maintenance work.

STI/PUB/848 (53 pp.; 1990) E ISBN 92–0–123190–3 C ISBN 92–0–523491–5 F ISBN 92–0–200192–8 R ISBN 92–0–400392–8 S ISBN 92–0–323591–4 Price: 240 Austrian schillings (€17.44)

SURVEILLANCE OF ITEMS IMPORTANT TO SAFETY IN NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-O8 (Rev. 1)

This guide provides guidance and recommendations on surveillanceactivities to ensure that structures, systems and components impor-tant to safety are available to perform their functions in accordancewith design intent and assumptions. The section on the surveillanceprogramme, its implementation, and the surveillance frequency andextent have been improved. The safety aspects of special tests andexperiments, surveillance activity optimization and early ageingsurveillance are emphasized.

Contents: Definitions; Introduction; Surveillance programme;Major surveillance requirements; Surveillance frequency and extent;Implementation of the surveillance programme; Administrativeaspects; Annex: Examples of parameters, systems, structures andcomponents of different types of reactor plants requiring surveil-lance.

STI/PUB/849 (61 pp.; 1990) E ISBN 92–0–123290–X C ISBN 92–0–500292–5 F ISBN 92–0–200595–8 R ISBN 92–0–400492–4 S ISBN 92–0–323691–0 Price: 240 Austrian schillings (€7.44)

MANAGEMENT OF NUCLEAR POWER PLANTS FOR SAFE OPERATION: A Safety Guide Safety Series No. 50-SG-O9

This guide identifies the main objectives and responsibilities ofmanagement with respect to the safe operation of nuclear powerplants. It discusses the factors to be considered in structuring theoperating organization to meet these objectives, in assigning theresponsibilities to units and individuals within the organization in anunambiguous manner, in establishing the management program-mesfor ensuring that all safety requirements are met and in providing theservices and facilities needed for the accomplishment of these tasks.

Contents: Introduction; Management objectives and respon-sibili-ties; Structuring the operating organization; Managementprogrammes; Information and liaison; Supporting functions; Appen-dix A: Development of instructions and procedures; Appendix B:Development of operating and maintenance procedures.

STI/PUB/660 (56 pp., 3 figures; 1984) E ISBN 92–0–123984–X C ISBN 92–0–523791–4 F ISBN 92–0–223984–3R ISBN 92–0–423386–9 S ISBN 92–0–323085–8 Price: 210 Austrian schillings (€15.26)

SAFETY ASPECTS OF CORE MANAGEMENT AND FUEL HANDLING FOR NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-O10

This guide addresses the safety objectives of core management, thetasks which have to be accomplished to meet these objectives andthe activities undertaken to perform these tasks. These include thepreparation of specifications for procurement, loading, utilizing,unloading and testing of fuel and core components. Maintenanceand surveillance requirements, the prediction and monitoring of coreconditions to evaluate the nuclear and thermal performance, andfurther safety aspects are covered.

Contents: Introduction; Core management; Handling of unirradi-ated fuel; Implementation of the fuelling plan; Irradiated fuelstorage; Core component handling; Preparation for fuel dispatch;Surveillance related to core management; Administrative and orga-nizational aspects; Records; Annex I: Baseline information relatingto core management.

STI/PUB/685 (40 pp., 1985) E ISBN 92–0–123085–0 F ISBN 92–0–223486–8 R ISBN 92–0–423387–7 S ISBN 92–0–323286–9 Price: 170 Austrian schillings (€12.35)


43

OPERATIONAL MANAGEMENT FOR RADIOACTIVE EFFLUENTS AND WASTES ARISING IN NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-O11

This guide covers the provisions to be made by the operating orga-nization prior to and during the commissioning and operating phasesof a nuclear power plant in order to keep the radiological impact onthe environment and the radiation exposure of the general public aslow as is reasonably achievable. It discusses the main sources ofradioactive wastes and the means available for their minimization,the classification and segregation of these wastes and the wastemonitoring programmes on-site.

Contents: Introduction; Objectives of the waste managementprogramme; Control of waste production; Waste treatment; Wastestorage; Waste transport; Effluent releases and environmental moni-toring; Abnormal conditions; Administration and organization;Annex I: Operating procedures; Annex II: Monitoring parameters ofwaste treatment systems; Annex III: Waste treatment systems.

STI/PUB/734 (52 pp.; 1986) E ISBN 92–0–123686–7 C ISBN 92–0–523391–9F ISBN 92–0–223687–9 R ISBN 92–0–424188–8 S ISBN 92–0–323487–X Price: 200 Austrian schillings (€14.53)

PERIODIC SAFETY REVIEW OF OPERATIONAL NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-O12

This guide supplements Safety Series No. 110: The Safety ofNuclear Installations, a safety fundamentals publication, and SafetySeries No. 50-C-O (Rev. 1): Code on the Safety of Nuclear PowerPlants: Operation. It primarily provides guidance on the conduct ofa periodic safety review (PSR) of an operational nuclear powerplant. A PSR is designed to take a comprehensive account ofimprovements in safety standards and operating practices, cumula-tive effects of plant ageing, modifications and feedback of operatingexperience, and developments in science and technology that haveoccurred over a ten year period. PSRs provide the means for deter-mining necessary or worthwhile changes aimed at maintaining highlevels of plant safety and harmonizing the safety of older plants withthat of modern plants.

Contents: Definitions; 1. Introduction; 2. Rationale for and objec-tive of periodic safety review; 3. Review strategy; 4. Safety factorsin a periodic safety review; 5. Roles and responsibilities; 6. Reviewprocedure; 7. Basis for acceptability of continued plant operation; 8.Post-review activities; Appendix: Elements of review.

STI/PUB/963 (50 pp., 4 figures; 1994) E ISBN 92–0–103894–1F ISBN 92–0–202197–XR ISBN 92–0–404796–8S ISBN 92–0–301596–5Price: 240 Austrian schillings (€17.44)

5. Quality Assurance

QUALITY ASSURANCE FOR SAFETY IN ➜NEWNUCLEAR POWER PLANTS AND OTHER NUCLEAR INSTALLATIONS: Code and Safety Guides Q1–Q14Safety Series No. 50-C/SG-Q

The revised Safety Code and its corresponding Safety Guidesreplace Safety Series No. 50-C-QA (Rev. 1), Code on the Safety ofNuclear Power Plants: Quality Assurance, and Safety Series Nos 50-SG-QA1 to 50-SG-QA11, and present new simplified basic require-ments and implementation methods for quality assurance in anuclear context. They provide recommendations to regulatorybodies in establishing regulatory requirements and in verifying theirimplementation, clearly formulate the responsibilities of the licenseein achieving improved quality and safety performance, and giveguidance on methods for fulfilling the basic requirements in amanner consistent with worldwide industry standards.

Contents: Glossary; Code; Safety Guides.

STI/PUB/1016 (364 pp., 6 figures; 1996)E ISBN 92–0–103696–5F ISBN 92–0–201998–3R ISBN 92–0–400898–9Price: 1040 Austrian schillings (€75.58)

S A F E T Y P R A C T I C E S E R I E S W I T H I N T H E N U S S P R O G R A M M E

APPLICATION OF THE SINGLE FAILURE CRITERION Safety Series No. 50-P-1

The relationship between the single failure criterion (see SafetySeries No. 50-C-D (Rev. 1), 3. Design) and system performance reli-ability is explained in order to determine the scope of the criterion’sapplication. A detailed discussion follows on the application princi-ples, the conditions during maintenance and testing of consequentialfailures, the relation to common cause failures and exemptions to thecriterion. The last section deals with single failure analysismethodology.

Contents: 1. Introduction; 2. Overview of relationship between thesingle failure criterion and reliability; 3. Application of the singlefailure criterion; 4. In-service maintenance and testing; 5. Conse-quential failures; 6. Common cause failures; 7. Exemptions to thesingle failure criterion; 8. Single failure analysis; Appendix: Exam-ples of methods for the determination of permissible outage times;Bibliography.


IN-SERVICE INSPECTION OF NUCLEAR POWER PLANTS Safety Series No. 50-P-2

Out of print.


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DATA COLLECTION AND RECORD KEEPING FOR THEMANAGEMENT OF NUCLEAR POWER PLANT AGEING Safety Series No. 50-P-3

This publication provides guidance on data requirements and aneffective and practical system for data collection and record keepingin relation to the evaluation and management of ageing and servicelife of nuclear power plant components. The application of the guid-ance will contribute to the safe and reliable operation of nuclearpower plants and will facilitate international information exchangeon ageing related component failures, malfunctions and degradation,since data collected using the same ground rules are easier toexchange and compare.

Contents: 1. Introduction; 2. General data needs for the evaluationand management of ageing; 3. Attributes of an effective data collec-tion and record keeping system; 4. General recommendations forimplementing the proposed data collection and record keepingsystem; Appendix I: Component specific data needs; Appendix II:Examples of effective data collection and record keeping systems;Appendix III: Guidance for implementation of an advanced datacollection and record keeping system; References; Glossary.


PROCEDURES FOR CONDUCTING PROBABILISTIC SAFETY ASSESSMENTS OF NUCLEAR POWER PLANTS (LEVEL 1) Safety Series No. 50-P-4

This safety practice report provides guidance on conducting a Level1 PSA for internal events in nuclear power plants. The main empha-sis is on the procedural steps of the PSA rather than the details of thecorresponding methods. The report is intended to assist technicalpersons managing or performing PSAs. A particular aim is topromote a standardized framework, terminology and form of docu-mentation for PSAs so as to facilitate external review of the results.The report not only describes methods, but also considers advan-tages and limitations of various approaches and indicates those mostwidely used to date.

Contents: 1. Introduction; 2. Management and organization;3. Identification of sources of radioactive releases and accidentinitiators; 4. Accident sequence modelling; 5. Data assessment andparameter estimation; 6. Accident sequence quantification; 7. Docu-mentation of the analysis: Display and interpretation of results;Appendix I: Example of a typical schedule for a Level 1 PSA;Appendix II: Contents of work specification.


SAFETY ASSESSMENT OF EMERGENCY POWER SYSTEMS FOR NUCLEAR POWER PLANTS Safety Series No. 50-P-5

This publication contains the questions which must be posed by thesafety assessor when reviewing the safety of an emergency powersystem in the design of a nuclear power plant. lt relates directly tothe safety requirements as laid down in Safety Series No. 50-SG-D7so that it is possible to confirm the compliance of a design to thesafety requirements. An extensive reference list of relevant interna-tional and national technical standards provides further guidance onacceptable design solutions.

Contents: 1. Introduction; 2. Safety assessment and licensing;3. Safety assessment and review guidance; 4. Reference listof recommended information for the safety assessment; 5. Biblio-graphy.


INSPECTION OF FIRE PROTECTION MEASURES AND FIREFIGHTING CAPABILITY AT NUCLEAR POWER PLANTS Safety Series No. 50-P-6

This publication outlines practices for inspecting the fire protectionmeasures at nuclear nuclear power plants in accordance with FireProtection in Nuclear Power Plants, published in 1992. The bookincludes a comprehensive fire safety inspection checklist of thespecific elements to be addressed when evaluating the adequacy andeffectiveness of the fire protection measures and manual fire fight-ing capability available at operating nuclear power plants. It isrecommended that this safety practice report be used in conjunctionwith Safety Guide No. 50-SG-D2 (Rev. 1).

Contents: 1. Introduction; 2. Methodology; 3. Evaluation andconclusions; 4. Inspection checklist.


TREATMENT OF EXTERNAL HAZARDS IN PROBABILISTICSAFETY ASSESSMENT FOR NUCLEAR POWER PLANTS Safety Series No. 50-P-7

This Safety Practice provides guidance on conducting a probabilis-tic safety assessment (PSA) for external hazards in nuclear powerplants, with application to the four specific types of hazard that areencountered and analysed most frequently: earthquakes, high winds,floods and man induced events. The methodology itself is generaland can be applied equally well to other types of hazard. Informa-tion is provided on the inclusion of external hazards in a Level 1 orLevel 2 PSA. A particular aim of the present publication, which ispart of a set of IAEA publications in preparation, is to promote astandardized framework, terminology and form of documentationfor conducting a PSA so as to facilitate external review and to inter-pret the results of such studies.

Contents: 1. Introduction; 2. Initiating events analysis; 3. Plantresponse analysis; 4. Analysis of in-plant accident phenomena andex-plant consequences.


PROCEDURES FOR CONDUCTING PROBABILISTIC SAFETYASSESSMENTS OF NUCLEAR POWER PLANTS (LEVEL 2): Accident Progression, Containment Analysis and Estimation of Accident Source Terms Safety Series No. 50-P-8

This Safety Practice provides guidance on how to conduct a Level 2probabilistic safety assessment (PSA) of a nuclear power plant forthe use of those performing or managing Level 2 PSAs. Emphasis isplaced on the procedural steps of a PSA rather than on detailedmethods. The aim is to standardize the framework, terminology and


45

forms of documentation for Level 2 PSAs to facilitate their externalreview. This report complements Safety Series No. 50-P-4, Proce-dures for Conducting Probabilistic Safety Assessments of NuclearPower Plants (Level 1).

Contents: 1. Introduction; 2. Management and organization;3. Familiarization with the plant and identification of design aspectsimportant to severe accidents; 4. Interface with Level 1 PSA: Group-ing of sequences; 5. Accident progression and containment analysis;6. Source terms for severe accidents; 7. Documentation of the analy-sis: Presentation and interpretation of results; Appendix I: Exampleof a typical schedule for a Level 2 PSA; Appendix II: Computercodes for severe accidents; Appendix III: Severe accident phenom-ena; Annex I. TC1 sequence for the Peach Bottom nuclear powerplant; Annex II. TMLU sequence for the Zion nuclear power plant.


EVALUATION OF FIRE HAZARD ANALYSES FOR NUCLEAR POWER PLANTS Safety Series No. 50-P-9

This publication provides a detailed list of the issues, and of some ofthe limitations, to be considered when evaluating the adequacy andeffectiveness of the fire hazard analysis of a nuclear power plant. Itis intended for assessors of fire hazard analyses. It further gives abroad description of the methodology to be used by operators inpreparing a fire hazard analysis for their own plant. It supplementsthe broad concepts of Safety Series No. 50-SG-D2 (Rev. 1), FireProtection in Nuclear Power Plants, and should be used in conjunc-tion with that guide.

Contents: 1. Introduction; 2. Fire hazard analysis; 3. Methodology;4. Fire assessment and recommendations; Annex: Normal operation(selectivity) of electrical circuit protection.


HUMAN RELIABILITY ANALYSIS IN PROBABILISTIC SAFETY ASSESSMENT FOR NUCLEAR POWER PLANTS Safety Series No. 50-P-10

This document presents a practical approach for incorporatinghuman reliability analysis (HRA) into probabilistic safetyassessment (PSA). It describes the steps needed and thedocumentation that should be provided both to support the PSAitself and to ensure effective communication of importantinformation arising from the studies. It also describes a frameworkfor analysing those human actions which could affect safety and forrelating such human influences to specific parts of a PSA.

Contents: 1. Introduction; 2. Framework of HRA in the context ofPSA; 3. Summary of the HRA process; 4. Integrating HRA into thePSA structure; 5. Pre-incident tasks and errors (Category A); 6. Inci-dent initiating errors (Category B); 7. Post-incident actions(Category C); 8. Documentation to support the PSA; 9. Issues relat-ing to the incorporation of HRA into PSA; References; Bibliogra-phy; Annex I: Example of the quantification and incorporation ofCategory A actions; Annex II: Examples of the incorporation ofCategory C actions/errors into PSA structures (fault trees and eventtrees); Glossary of acronyms.


ASSESSMENT OF THE OVERALL FIRE SAFETY ➜NEWARRANGEMENTS AT NUCLEAR POWER PLANTSSafety Series No. 50-P-11

This Safety Practice supplements Safety Guide No. 50-SG-D2 (Rev.1), Fire Protection in Nuclear Power Plants, by providing a detailedfire safety inspection checklist. This list is intended for use by qual-ified fire safety specialists in assessing the adequate implementationand effectiveness of the overall fire safety arrangements of an oper-ating nuclear power plant. The present publication should be used inconjunction with the above mentioned Safety Guide.

Contents: 1. Introduction: 1.1. Background; 1.2. Objective;1.3. Scope; 1.4. Structure; 2. Methodology: 2.1. Document review;2.2. Personnel interviews; 2.3. Direct observation; 2.4. Interpreta-tion issues; 3. Evaluation and conclusions; 4. Inspection checklist.


PROCEDURES FOR CONDUCTING ➜NEWPROBABILISTIC SAFETY ASSESSMENTS OF NUCLEAR POWER PLANTS (LEVEL 3): Off-Site Consequences and Estimation of Risks to the PublicSafety Series No. 50-P-12

This report on Level 3 Probabilistic Safety Assessments (PSAs)completes the series on procedures for conducting PSAs of nuclearpower plants. It provides insights into the relative importance ofaccident prevention and mitigative measures, expressed in terms ofthe adverse consequences for the health of the public and the conta-mination of land, air, water and foodstuffs. The relative effectivenessof emergency response planning aspects of off-site accidentmanagement and their economic impacts are another important partof a Level 3 PSA.

Contents: 1. Introduction; 2. Probabilistic consequence analysis; 3.Performing a Level 3 PSA; 4. Managing a Level 3 PSA; Annex I:Current developments in probabilistic consequence analysis; AnnexII: Selection of a consequence analysis code; Annex III: Samplestructure for a Level 3 PSA report.


ON-SITE HABITABILITY IN THE EVENT OF AN ACCIDENT AT A NUCLEAR FACILITYSafety Series No. 98

(See under Accident Response, p. 69)

POTENTIAL EXPOSURE IN NUCLEAR SAFETY — A Report by the International Nuclear Safety Advisory Group INSAG Series No. 9

The present report deals with the concept of potential exposure innuclear and radiation safety, discussing policy aspects, safety assess-ments, risk considerations and probabilities.

Contents: 1. Introduction; 2. Aspects of risk; 3. Policy for nuclearand radiation safety; 4. Safety assessments and risk considerations;


46

5. The implications of low probabilities; 6. Balancing potential andnormal exposures; 7. Conclusions; Annex. Probability theory and itsapplication in probabilistic safety assessment.

STI/PUB/992 (29 pp.; 1995)E ISBN 92–0–102495–9F ISBN 92–0–201696–8R ISBN 92–0–401996–4S ISBN 92–0–300797–2Price: 160 Austrian schillings (€11.63)

PREPARATION OF FIRE HAZARD ➜NEWANALYSES FOR NUCLEAR POWER PLANTS Safety Reports Series No. 8

The present report provides a framework for preparing a compre-hensive fire hazard analysis for new or existing nuclear powerplants, and includes a detailed description of the issues to be consid-ered in determining the adequacy of fire protection with respect toplant nuclear safety. It supplements Safety Guide No. 50-SG-D2(Rev. 1) (1992): Fire Protection in Nuclear Power Plants.

Contents: 1. Introduction; 2. Fire hazard analysis; 3. Methods to befollowed in preparing the fire hazard analysis; 4. Data collection;5. Analysis of fire growth; 6. Consequence analysis; 7. Evaluation ofthe adequacy of fire safety; 8. Considerations before makingimprovements in fire safety; 9. Repetition of analysis; Annex I:Sample data collection tables; Annex II: Prefire fire fighting strat-egy; Annex III: Effect of the ventilation systems; Annex IV; Direct,indirect and secondary effects of the fire and fixed fire extinguishingsystems; Annex V: Other effects of a fire; References; Bibliography:Fire safety engineering calculations.


PROBABILISTIC SAFETY ASSESSMENT — A Report by the International Nuclear Safety Advisory Group Safety Series No. 75-INSAG-6

Probabilistic safety assessment (PSA) has contributed significantlyto the understanding of how best to ensure the safety of nuclearpower plants. By means of PSA, a nuclear power plant, including itssafety systems and installations, can be analysed in its entirety. Therapid development of the method has resulted in its extensive use.This report reviews the general bases of PSA, emphasizing its meritsand limits as well as the general lines of the future development ofthat methodology and its applications.

Contents: 1. Introduction; 2. Capabilities and limitations of themethodology of PSA; 3. Further development of methodology;4. Guidelines for presentation and interpretation of PSA results; 5.How should PSA be used in the future?; 6. Conclusions.


PROVISION OF OPERATIONAL RADIATION PROTECTIONSERVICES AT NUCLEAR POWER PLANTS Safety Series No. 103


QUALITY MANAGEMENT FOR NUCLEAR POWER PLANT OPERATION: A Manual Technical Reports Series No. 315

This manual has been developed to assist plant managers infulfilling their responsibility with regard to the control and directionof quality and of quality assurance activities in nuclear power plantoperation. It emphasizes quality objectives for nuclear power plantoperations and gives highlighted practices complemented by typicalexamples of forms and procedures. The selected activities comprisethose where it was felt that practical advice is generally needed.

Contents: 1. Introduction; 2. Quality management; 3. Competenceof personnel; 4. Operations; 5. Maintenance; 6. Deficiencies andcorrective actions; 7. Technical support; 8. Radiological safety;9. Emergency preparedness; 10. Feedback; Appendix A: Summaryof plant superintendent’s involvement and reviews listed in themanual; Appendix B: Typical organization of nuclear power plantoperations, showing the functions allocated to superintendents andmanagers; Annex I: Model of the implementation process of aquality assurance programme; Annex II: Quality seminar for super-visors; Annex III: Typical nuclear power plant interfaces; Annex IV:Development of personnel; Annex V: Sample of a jumper record;Annex VI: Control room panel checksheet; Annex VII: Key featuresof a significant event report (SER) procedure; Annex VIII: Exampleof a significant event report; Annex IX: Significant event classifica-tion code; Annex X: Work authorization; Annex XI: Application foroperator administered work permit or condition guarantee; AnnexXII: Work permit; Annex XIII: Work permit or condition guarantee;Annex XIV: ‘Order to operate’ form; Annex XV: ‘Do not operate’tags; Annex XVI: Human performance worksheet; Annex XVII:Mechanical/maintenance work report; Annex XVIII: Deficiencyreport; Annex XIX: ‘Proposed change’ form; Annex XX: Typicalquality assurance auditing schedule; Annex XXI: Typical perfor-mance measures.


RADIONUCLIDE SOURCE TERMS FROM SEVERE ACCIDENTS TO NUCLEAR POWER PLANTS WITH LIGHT WATER REACTORS — A Report by the International Nuclear Safety Advisory Group Safety Series No. 75-INSAG-2

This report presents the views of the IAEA’s International NuclearSafety Advisory Group INSAG on the source term issue for LWRsof existing designs. The report considers the present status of sourceterm research and analysis and their implications. It identifies prob-lems which remain to be resolved and indicates areas where workshould be initiated to improve safety.

Contents: Introduction; Purpose; Probabilistic safety analysis;General issues; High source term sequences; Early containmentfailure; Remobilization of fission products; Bypass of containment;Other issues; Reduction of risk and source term through accidentprevention, management and mitigation; Conclusions; Bibliogra-phy; Appendix: Implications of the source term from the Chernobylaccident.



47

REACTIVITY ACCIDENTS Technical Reports Series No. 354

The present report consists of two parts. The first and larger part(Sections 1–4) provides an overview of reactivity accidents: howthey can arise, the basic principles of the defence against them,methods of analysis and acceptance criteria. The second partsummarizes more recent work on ‘beyond-design-basis’ reactivityaccidents.

Contents: 1. Background and overview; 2. Design basis accidents;3. Experiments on fuel behaviour; 4. Methods for analysing designbasis accidents; 5. Beyond-design-basis accidents; 6. Conclusions.

STI/DOC/10/354 (52 pp.; 1993)ISBN 92–0–101493–7 Price: 220 Austrian schillings (€15.99)

RECOVERY OPERATIONS IN THE EVENT OF A NUCLEAR ACCIDENT OR RADIOLOGICAL EMERGENCYProceedings Series


REGULATORY INSPECTION OF THE IMPLEMENTATION OF QUALITY ASSURANCE PROGRAMMES: A ManualTechnical Reports Series No. 296

(See under Quality Management, p. 79)

REGULATORY PRACTICES AND SAFETY STANDARDS FOR NUCLEAR POWER PLANTS Proceedings Series

Proceedings of a symposium, jointly organized by the FederalRepublic of Germany, IAEA and OECD/NEA, Munich, 7–10 No-vember 1988. The overall emphasis was placed on the internationalaspects of nuclear safety.

Contents: Opening session; National regulatory practices andsafety standards; National regulatory systems; Implementation ofregulatory practices (technical issues); Implementation of regulatorypractices (operational aspects); Development and trends in safetystandards and practices; International aspects; Implementation ofdevelopments in safety standards and practices (Panel I); Interna-tional harmonization of safety standards and practices — Need,possibilities and limitations (Panel II).


REVIEWING THE SAFETY OF ➜NEWEXISTING NUCLEAR POWER PLANTSProceedings Series

Proceedings of a symposium organized in co-operation withOECD/NEA, Vienna, 8–11 October 1996. The symposium was afollow-up to the 1991 International Conference on The Safety ofNuclear Power: Strategy for the Future and will be remembered asthe initiating force behind the Convention on Nuclear Safety, whichentered into force on 24 October 1996. The goal was to review theprogress made in implementing the recommendations of the 1991Conference relating to the safety of existing nuclear power plants,

and to make available to all those involved in maintaining the safetyof nuclear power plants information on effective methods, practicesand criteria for safety review and operating experience feedbacksystems.

Contents: Opening session; Elements of the nuclear power safetystrategy; Ongoing safety reviews; Periodic safety reviews: Regula-tory perspective; Periodic safety reviews: Utility perspective; Safetyassessment methods and experience; Safety reviews of specialissues; Feedback of operating experience I; Information databasesand operating experience feedback; Feedback of operating experi-ence II; Summary of the panel and the symposium.


SAFE ENCLOSURE OF SHUT DOWN NUCLEAR INSTALLATIONSTechnical Reports Series No. 375

This publication gives a concise description of factors (safety-related, technical and economical) that are relevant to the selectionof a decommissioning strategy, with particular reference to the safeenclosure option as a precursor to the dismantling of a nuclearinstallation. It is complemented by data on selected shut downinstallations. Aspects such as radioactive inventory, reasons for thechosen decommissioning strategy and systems kept operational oron stand-by are highlighted.

Contents: 1. Introduction; 2. Objective; 3. Scope; 4. Structure;5. Considerations influencing the choice of decommissioning strat-egy; 6. General overview of strategies and regulatory considerations;7. Radiological considerations in safe enclosure; 8. Preparation forsafe enclosure; 9. Management of safe enclosure; 10. Public safetyand environmental aspects; 11. Summary and conclusions; Appen-dix: Problems of the application of safe enclosure in relation tovarious plant conditions; Annex A. Description of selected cases ofsafe enclosure.


SAFE MANAGEMENT OF THE OPERATING ➜NEWLIFETIMES OF NUCLEAR POWERPLANTS — A Report by the InternationalNuclear Safety Advisory GroupINSAG Series No. 14

The present report deals with a general approach to the safe manage-ment of the operating lifetimes of nuclear power plants, whichrequires a continuing quest for excellence. It also responds to theconcerns about maintaining adequate safety levels at ageing plants,even beyond their design lifetimes.

Contents: 1. Introduction; 2. General safety objective; 3. Ageingprocesses; 4. Considerations related to design and construction;5. Comparison with the design basis; 6. Review of the referencesafety levels; 7. Safety reviews; 8. Infrastructure support for safemanagement of the operating lifetimes; 9. Managementresponsibilities.


STI/PUB/1085 (23 pp., 1999)ISBN 92–0–103099–1Price: 140 Austrian schillings (€10.17)


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SAFETY ASPECTS OF THE AGEING AND MAINTENANCE OF NUCLEAR POWER PLANTS Proceedings Series

Proceedings of a symposium, Vienna, 29 June to 3 July 1987. Thesymposium, the first one organized by the IAEA on this subject, wasto provide a forum for the exchange of technical information on theapproaches to ageing at nuclear power plants and the activities beingcarried out to mitigate age related effects and for the exchange oftechnical and economic information on approaches to plant lifeextension.

Contents: General safety aspects of ageing; Conceptual approach tothe safety aspects of NPP ageing; Methods for critical componentsand systems determination; Methods and provisions to handlingageing phenomena during NPP operation; General aspects of NPPlife extension; Technological aspects of NPP life extension.


SAFETY CULTURE — A Report by the International Nuclear Safety Advisory Group Safety Series No. 75-INSAG-4

This report by the IAEA’s International Nuclear Safety AdvisoryGroup INSAG describes the concept of ‘Safety Culture’ inconnection with nuclear plant safety in relation to both organi-zations and individuals engaged in nuclear power activities. Itprovides a basis for judging the effectiveness of the safety culture inspecific cases in order to identify potential improvements.

Contents: Summary; 1. Introduction; 2. Definition and character ofSafety Culture; 3.1. Requirements at policy level; 3.2. Requirementson managers; 3.3. Response of individuals; 4. Tangible evidence;4.1. Government and its organizations; 4.2. Operating organization;4.3. Supporting organizations; 5. Concluding comments; Appendix:Safety Culture indicators.

STI/PUB/882 (31 pp., 1 figure; 1991) E ISBN 92–0–123091–5 F ISBN 92–0–223191–5 R out of printS ISBN 92–0–323491–8 Price: 140 Austrian schillings (€10.17)

SAFETY ISSUES FOR ADVANCED ➜NEWPROTECTION, CONTROL AND HUMAN–MACHINE INTERFACE SYSTEMS IN OPERATING NUCLEAR POWER PLANTSSafety Reports Series No. 6

This Safety Report identifies and describes safety and licensingissues reflecting international experience and practices and offersgood practices and effective safety approaches to digital instrumen-tation and control (I&C) retrofits in operating nuclear power plants.It provides valuable guidance to all those involved in upgradingprotection, control and human–machine interface systems in nuclearpower plants.

Contents: 1. Introduction; 2. Safety categorization and standards;3. Safety issues of advanced systems; 4. Methodologies to addresssafety issues; 5. Safety approaches for the human–machine inter-face; 6. Safety aspects of the upgrade process for advanced protec-tion, control and human–machine interface systems; Glossary.


SELECTED SAFETY ASPECTS OF WWER-440 ➜NEWMODEL 213 NUCLEAR POWER PLANTS

Final Report of the IAEA Project on Evaluation of Safety Aspectsfor WWER-440 Model 213 Nuclear Power Plants — ReferencePlant: Bohunice NPP V2 (Slovakia)

In 1991, the Atomic Energy Commission (AEC) of the formerCzechoslovakia requested that an evaluation of the safety aspects ofthe WWER-440 model 213 nuclear power plant be undertaken underthe auspices of the IAEA. The prime objective of the project was toco-ordinate and integrate assistance given to national organizationsin studying selected aspects of safety for the same type of reactors.Consequently, the study integrated these results. This reportprovides a comprehensive review of the conduct and the final resultsof the project. It summarizes both the detailed material publishedearlier in IAEA-TECDOCs (Nos 742, 803, 810, 811 and 848) andother material. It will be useful to everyone working in the field ofWWER safety, and in particular to experts planning, executing orreviewing studies related to WWER safety.

Contents: 1. Introduction; 2. Plant design features; 3. Design basis;4. Experimental design verification; 5. Design basis accident analy-sis; 6. Analysis of external and internal hazards; 7. Beyond designbasis accident analysis and accident management; 8. Operationalexperience; 9. Concluding summary; Annex I. List of working mate-rials and internal reports (1991–1994); Annex II: List of projectmeetings and expert assignments; Annex III: Design basis accidentsproposed for safety reassessment of WWER-440-213 NPPs;Annex IV: International peer review summary.


SEVERE ACCIDENTS IN NUCLEAR POWER PLANTS Proceedings Series

Proceedings of a symposium jointly organized with OECD/NEA,Sorrento, Italy, 21–25 March 1988. The contents of the proceed-ings represent a wide spectrum of topics and should provide anunderstanding of the issue of beyond the design basis accidents,quite frequently called ‘severe accidents’. The papers give anoverview of different national approaches, with the overall empha-sis on preventive, mitigative and accident management measures.The most important outcome of the symposium was a clear aware-ness of accident management questions which were among the mostcontroversial issues discussed.

Contents: (Vol. 1) National positions and practices on severe acci-dents; Accident initiation and analysis; Non-water-cooled nuclearpower reactors; (Vol. 2) Accident research and development; Acci-dent management.

STI/PUB/782 (Vol. 1: 505 pp., 148 figures; Vol. 2: 772 pp.,225 figures; 1988) 1: ISBN 92–0–020188–1 2: ISBN 92–0–020288–8 Price: Vol. 1: 1250 Austrian schillings (€90.84)


SOFTWARE IMPORTANT TO SAFETY IN NUCLEAR POWER PLANTS Technical Reports Series No. 367

This report provides guidance on current practices, documentingtheir strengths and weaknesses in dealing with the important issuesof software engineering that nuclear power plant system designers,


49

software producers and regulators are facing. It focuses on safetycritical applications of general purpose processors controlled bycustom developed software; however, it should also have applicationin safety related applications and in other types of computers.

Contents: 1. Introduction; 2. Applicability of existing safety princi-ples to software important to safety in nuclear power plants; 3. Theengineering context; 4. Management; 5. Modelling for requirementanalysis and design; 6. Documentation; 7. Programming; 8. Verifi-cation and validation; 9. Testing; 10. Figures of merit; 11. Mainte-nance; 12. Tool support; 13. Use of existing software; 14. Personnelqualification and training; 15. Balance in software based systems;Annex I: Existing standards and standardization work relating tosoftware important to safety in nuclear power plants; Annex II:Application of software based systems important to safety in nuclearpower plants: Experience of Member States.

STI/DOC/010/367 (169 pp., 1 figure; 1994) ISBN 92–0–101594–1 Price: 560 Austrian schillings (€40.70)

SOURCE TERM EVALUATION FOR ACCIDENT CONDITIONSProceedings Series

Proceedings of a symposium organized in co-operation with theUnited States Nuclear Regulatory Commission and Battelle Colum-bus Laboratories, Columbus, Ohio, from 28 October to 1 November1985. Five topics related to source term evaluation were selected forreview and discussion, namely in-vessel release, retention in theprimary circuit, ex-vessel release, retention in the containment andrelease from the plant.

Contents: Opening session; In-vessel release; Retention in theprimary circuit; Ex-vessel release; Retention in containment;Containment challenges (Panel A); Release from the plant; Regula-tory implications (Panel B).


SUMMARY REPORT ON THE POST-ACCIDENT REVIEWMEETING ON THE CHERNOBYL ACCIDENT — A Report by the International Nuclear Safety Advisory Group Safety Series No. 75-INSAG-1

This report was prepared after the Post-Accident Review Meeting onthe Chernobyl Accident, Vienna, 25–29 August 1986. A team ofSoviet experts who presented a report on the accident at the Cher-nobyl nuclear power station on 26 April 1986 jointly with INSAGmembers and other associated experts prepared this agreed report onthe accident and formulated recommendations for follow-up actionsby the IAEA.

Contents: Executive summary; Introduction; 1. The accident atChernobyl Unit 4; 2. The radionuclide release from the accident; 3.The response at the site; 4. Radiation protection aspects of the acci-dent; 5. Safety issues to be pursued; 6. General observations andprovisional conclusions; 7. Recommendations; Annex: RBMK reac-tors at Chernobyl nuclear power station Units 3 and 4.


SURVEY OF EXPERIENCE WITH DRY STORAGE OF SPENT NUCLEAR FUEL AND UPDATE OF WET STORAGE EXPERIENCE Technical Reports Series No. 290

This report presents data on the dry storage of spent nuclear fuel andrecent information on wet storage, transportation and rod consolida-tion. The amount of spent fuel arisings will increase significantly inthe next one or two decades. In view of the large quantities of spentfuel discharged from nuclear power plants and the expected futuredischarges, many countries are involved in the construction ofstorage facilities and in the development of effective methods forspent fuel surveillance and monitoring to ensure reliable and safeoperation.

Contents: Summary and conclusions; 1. Introduction; 2. Keyconsiderations in the dry storage of zirconium alloy clad fuel;3. Spent fuel description and history; 4. Dry storage technology;5. Spent fuel behaviour during storage; 6. Performance of facilitiesand test programmes; 7. Other experience/developments (wet anddry); 8. Update on wet storage; 9. Transport; Appendix A: Ques-tionnaire, glossary, and acronyms and abbreviations; Appendix B:Special cases; Appendix C: Proposed dry storage facilities; Appen-dix D: Synopsis of USSR experience in spent fuel storage and trans-portation; Appendix E: Detailed description of casks in use andunder development in the USA; Appendix F: Report ofBNFL/PNTL and NTL transport flasks (casks) (United Kingdom);Bibliography.


SYSTEMS FOR REPORTING UNUSUAL EVENTS IN NUCLEAR POWER PLANTS Safety Series No. 93

This publication provides guidance for establishing a system for thecollection, assessment and distribution of information on unusualevents of safety significance in nuclear power plants, on a nationaland international basis. It also describes the concepts, contents andprocedures of the IAEA Incident Reporting System (IAEA-IRS). Itis directed to both the utility personnel and the regulatory staff ofnuclear power plants.

Contents: Introduction; Part I: A national system; Part II: IAEAIncident Reporting System (IAEA-IRS); Appendix I: Unusual eventreporting categories; Appendix II: Standard format and contents ofIRS reports; Appendix III: Checklist for the preparation of an IRSreport; Appendix IV: Classification of lessons learned; Annex I:Coded watchlist; Annex II: Dictionary of codes; Definitions.

STI/PUB/801 (66 pp.; 1989)

E out of printF ISBN 92–0–223390–X R out of printS ISBN 92–0–323090–4 Price: 240 Austrian schillings (€17.44)

THE CHERNOBYL ACCIDENT: UPDATING OF INSAG-1 — A Report by the International Nuclear Safety Advisory Group Safety Series No. 75-INSAG-7

The purpose of this report is to update findings of the InternationalNuclear Safety Advisory Group’s Summary Report on the Post-Accident Review Meeting on the Chernobyl Accident (INSAG-1),published in September 1986, in the light of further information thathas been revealed since that meeting. INSAG stands by the general


50

conclusions of INSAG-1 about the accident’s causes and their impli-cations for the safety of the Chernobyl type light water cooledgraphite moderated RBMK reactors. However, the new information,which derives from studies made in the then USSR on the physicalorigins of the accident, has led INSAG to shift the emphasis of itsconclusions from the actions of the operating staff to faulty designof the reactor’s control rods and safety systems. Deficiencies in theregulation and management of safety matters throughout the Sovietnuclear power industry have also been revealed and are discussed.Two detailed Soviet reports on the causes and circumstances of theChernobyl accident, translated into English by the IAEA, and astatement of measures that have been taken to enhance the safety ofRBMK reactors are included.

Contents: 1. Introduction; 2. Features of the reactor; 3. Theaccident; 4. More recent analyses of the fault scenario; 5. Views ofINSAG; 6. Conclusions on factors contributory to the accident;Appendix: Measures to improve the safety of RBMK plants; AnnexI: Report by a commission to the USSR State Committee for thesupervision of safety in industry and nuclear power; Annex II:Report by a working group of USSR experts.

STI/PUB/913 (135 pp., 16 figures; 1992) E ISBN 92–0–104692–8F ISBN 92–0–201796–4R ISBN 92–0–400593–9S ISBN 92–0–300194–8Price: 440 Austrian schillings (€31.98)

THE ROLE OF PROBABILISTIC SAFETY ASSESSMENT AND PROBABILISTIC SAFETY CRITERIA IN NUCLEAR POWER PLANT SAFETY Safety Series No. 106

(See under Safety Analysis, p. 78)

THE SAFETY OF NUCLEAR INSTALLATIONS:A Safety FundamentalSafety Series No. 110

This Safety Fundamentals publication presents an internationalconsensus on the basic concepts underlying the principles for theregulation, management of safety and operation of nuclear installa-tions. It forms a top level publication in the hierarchy of the IAEASafety Series. In conjunction with this publication, Safety Stan-dards, Safety Guides and Safety Practices provide detailed require-ments and recommendations for activities relating to siting, design,quality assurance, operation and regulation of nuclear installations.

Contents: 1. Introduction; 2. Safety objectives; 3. Legislative andregulatory framework; 4. Management of safety; 5. Technicalaspects of safety; 6. Verification of safety; Definitions; Annex: Theconcept of risk: Methods of risk evaluation and limitation.


THE SAFETY OF NUCLEAR POWER — A Report by the International Nuclear Safety Advisory Group Safety Series No. 75-INSAG-5

This report gives an account of the history of nuclear power plantsafety, covering the important elements from safety in the earliestdays to lessons learned from accidents and current reactor safetyprinciples. The report concentrates on light and heavy water moder-

ated reactors, by far the most prevalent types. It concludes that forthese types of reactors, levels of safety are in reasonable agreementwith the present INSAG quantitative targets for probabilities of coremelt and radioactive releases. The report is directed at an educatedgeneral public.

Contents: Summary; Prologue; 1. Important elements of the historyof nuclear plant safety; 2. Current reactor safety principles; 3. Safetyof nuclear plants; 4. Nuclear fuel cycle; 5. Features desired in futureplants; 6. Continued improvement of nuclear power plant safety;7. Conclusions; Appendix I: IAEA safeguards against proliferationof nuclear weapons; Appendix II: Nuclear reactor radiation and itseffects; Appendix III: Relative health risks in electricity generation.

STI/PUB/910 (83 pp., 1 figure; 1992) E ISBN 92–0–100192–4 F ISBN 92–0–200393–1 R ISBN 92–0–400294–8 S ISBN 92–0–300293–6 Price: 300 Austrian schillings (€21.80)

THE SAFETY OF NUCLEAR POWER: STRATEGY FOR THE FUTURE Proceedings Series

Proceedings of a conference, Vienna, 2–6 September 1991. Theconference was directed to decision makers on nuclear safety andenergy policy at the technical policy level. Its objective was toreview the nuclear power safety issues on which internationalconsensus would be desirable, to address the concerns on nuclearsafety expressed by the United Nations World Commission on Envi-ronment and Development, and to formulate recommendations forfuture actions by national and international authorities to advancenuclear safety to the highest level, including proposals for futureIAEA activities. The major issues under discussion were: funda-mental principles for the safe use of nuclear power; ensuring andenhancing safety of operating plants; approach to nuclear powerplants built to earlier safety standards; the next generation of nuclearpower plants; and final disposal of radioactive waste.

Contents: Opening speeches; Issue overviews, summary discus-sions of substantive topics, conclusions and recommendations;Major findings of the conference and president’s closing statement;Background papers; Authorities of the conference and list ofparticipants.


TREATMENT OF INTERNAL FIRES ➜NEWIN PROBABILISTIC SAFETY ASSESSMENT FOR NUCLEAR POWER PLANTSSafety Reports Series No. 10

This Safety Report provides information on good practices inconducting probabilistic safety assessment (PSA) for fires in landbased nuclear power plants. It has been developed in response to theincreasing attention being given to PSA worldwide and is intendedto facilitate the implementation of the risk based approach to firesafety assessment for both new and operating nuclear power plants.

Contents: 1. Introduction; 2. General overview of a fire PSAproject; 3. Preparation phase (Tasks 1–4); 4. Screening phases(Tasks 5 and 6); 5. Detailed analysis (Task 7); 6. Special issues;7. Analysis of the results (Tasks 8 and 9); 8. Documentation of theanalysis (Task 10); 9. Ex-core sources of radioactive material;Appendix I: Information required from and in addition to the inter-nal events PSA model; Appendix II: Essential equipment malfunc-tions resulting form fire induced damage to non-essential circuits;


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Appendix III: Use of detailed analysis methods; Appendix IV: Firepropagation event tree; Appendix V: Potential for loss of the alter-nate shutdown capability during a control room fire.


USE OF PROBABILISTIC SAFETY ASSESSMENT FOR OPERATIONAL SAFETY — PSA ‘91Proceedings Series

(See under Safety Analysis, p. 78)

Research Reactors

CODE ON THE SAFETY OF NUCLEAR RESEARCH REACTORS: DESIGN Safety Series No. 35-S1

This publication presents international consensus principles usefulin the design of a research reactor. lt is complemented by SafetySeries No. 35-S2, Code on the Safety of Nuclear Research Reactors:Operation. Both publications provide an overview on basic princi-ples and requirements for the safety of research reactors and criticalassemblies, including the essential safety requirements for siting,quality assurance and regulatory control. These codes supersede the1984 edition of Safety Series No. 35, Safe Operation of ResearchReactors and Critical Assemblies.

Contents: Definitions; 1. Introduction; 2. Safety objectives;3. Regulatory supervision; 4. Siting requirements; 5. General designrequirements; 6. Specific design requirements; Appendix: Selectedpostulated initiating events; Annex: Selected safety functions.


CODE ON THE SAFETY OF NUCLEAR RESEARCH REACTORS: OPERATION Safety Series No. 35-S2

This publication presents international consensus principles usefulin the operation of a research reactor. lt is complemented by SafetySeries No. 35-S1, Code on the Safety of Nuclear Research Reactors:Design. Both publications provide an overview on basic principlesand requirements for the safety of research reactors and criticalassemblies, including the essential safety requirements for siting,quality assurance and regulatory control. These codes supersede the1984 edition of Safety Series No. 35, Safe Operation of ResearchReactors and Critical Assemblies.

Contents: Definitions; 1. Introduction; 2. Safety objectives;3. Regulatory supervision; 4. Responsibilities for safe operation;5. Safety analysis for operation; 6. Operational limits and condi-tions; 7. Operating procedures; 8. Commissioning; 9. Maintenance,period testing and inspection; 10. Core management and fuelhandling; 11. Records and reports; 12. Reactor utilization; 13. Modi-fications; 14. Radioactive wastes; 15. Radiation protection;16. Emergency planning; 17. Security; 18. Quality assurance;19. Decommissioning; Annex: Examples of operational aspects ofresearch reactors that require particular attention in a quality assur-ance programme.


SAFETY ASSESSMENT OF RESEARCH REACTORS AND PREPARATION OF THE SAFETY ANALYSIS REPORT Safety Series No. 35-G1

This Safety Guide, a companion document to Safety Series Nos 35-S1 and 35-S2, is part of a set of publications in the IAEA SafetySeries dealing with all the important areas of research reactor safetyincluding Safety Standards, Safety Guides and Safety Practices. Itpresents guidelines, approved by international consensus, for thepreparation, review and assessment of the safety documentation(Safety Series No. 35-S1) and for the preparation of the SafetyAnalysis Report (SAR) (Safety Series No. 35-S2). In addition, it ismost applicable during the design and construction stage of researchreactors, as well as during relicensing or reassessment of alreadyexisting reactors.

Contents: 1. Introduction; 2. Requirements for safety assessment inthe licensing process for a research reactor; 3. Preparation of thesafety analysis report; 4. Performance of the review and assessment;Appendix: Contents of a Safety Analysis Report; Annex I: Safetyanalysis approach and methods; Annex II: Examples of input para-meters and initial conditions; Annex III: Examples of items to beconsidered in the reactor description; Annex IV: Typical sources ofradioactive material or radiation fields in a research reactor.


SAFETY IN THE UTILIZATION AND MODIFICATION OF RESEARCH REACTORS Safety Series No. 35-G2

This Safety Guide, part of a set of publications in the IAEA SafetySeries dealing with all the important areas of research reactor safetyincluding Safety Standards, Safety Guides and Safety Practices,develops the general concepts presented in Safety Series Nos 35-S1and 35-S2 and should be read in conjunction with them. It presentsguidelines, approved by international consensus, for the safe utiliza-tion and modification of research reactors to ensure that theseprojects are implemented without undue risks to personnel, thepublic, the environment or the reactor. While the guide is mostapplicable to existing reactors, it is also recommended for use byorganizations planning to put a new reactor into operation.

Contents: 1. Introduction; 2. Organization and responsibilities;3. Safety assessment, categorization and approval routes;4. General and specific safety requirements for design; 5. Pre-implementation phase of a utilization or modification project;6. Implementation phase of a utilization or modification project;7. Post-implementation phase of a utilization or modificationproject; 8. Operational safety requirements for experiments;9. Safety considerations in the handling, dismantling, post-irradiation examination and disposal of experimental devices;10. Safety aspects of out-of-reactor installations; 11. Quality assur-ance of experiments and modifications; Annex I: Categorizationcriteria; Annex II: Justification of a project.


N U C L E A R P O W E R P L A N T S — R E S E A R C H R E A C T O R S

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Radiation Sources and Accelerators

EMERGENCY PLANNING AND PREPAREDNESS FOR ACCIDENTS INVOLVING RADIOACTIVE MATERIALS USED IN MEDICINE, INDUSTRY, RESEARCH AND TEACHING Safety Series No. 91


PHYSICAL PROTECTION OF NUCLEAR ➜NEWMATERIALS: Experience in Regulation, Implementation and Operations

Proceedings of a conference, Vienna, 10–14 November 1997, whichaimed at fostering the exchange of information, practices and expe-rience in order to assist States, where appropriate, in upgrading theirprogrammes for the physical protection of nuclear materials andcombating illicit trafficking. It focused on the regimes, equipmentand procedures currently used to minimize the possibilities of unau-thorized removal of nuclear materials, whether by terrorists, crimi-nals or facility employees, and to protect against sabotage.

Contents: Opening session; Contemporary and emerging issues;Experience in regulation I; Experience in regulation II; Implementa-tion at facilities; Programme assessment and co-operation I;Programme assessment and co-operation II; Hardware/software;Illicit trafficking in nuclear materials; Transportation; Future consid-erations and summary of sessions.


RADIATION PROTECTION AND SAFETY ➜NEWIN INDUSTRIAL RADIOGRAPHYSafety Reports Series No. 13

This Safety Report summarizes good and current state of the artpractices in industrial radiography and provides technical advice onradiation protection and safety. It contains information explainingthe responsibilities of regulatory authorities, operating organiza-tions, workers, equipment manufacturers and client organizations,with the intention of enhancing radiation protection and safety.

Contents: 1. Introduction; 2. Objectives of radiation protection andsafety; 3. Organizational responsibilities; 4. Types of exposuredevices; 5. Design and use of shielded enclosures (fixed facilities);6. Site radiography procedures; 7. Storage, movement and transportof radiographic sources and exposure devices; 8. Emergencyresponse planning; References; Glossary.


RADIATION PROTECTION AND THE ➜NEWSAFETY OF RADIATION SOURCES: A Safety FundamentalSafety Series No. 120

Jointly sponsored by FAO, IAEA, ILO, OECD/NEA, PAHO andWHO

This Safety Fundamentals publication provides a coherent set ofobjectives and principles for protection against ionizing radiationand for ensuring safety in the use of radiation sources. Theprotection objective and the safety objective, together with theeleven principles that have to be applied to achieve them, represent

an international consensus. They provide the basis for the require-ments in IAEA Safety Standards for the control of occupational,public and medical exposures and for the safety of sources. TheSafety Fundamentals also provide an insight into the general systemof protection and safety for those at senior levels in government andregulatory bodies and those responsible for making decisions relat-ing to the uses of radiation in medicine, industry, agriculture,research and other areas.

Contents: 1. Introduction; 2. Biological effects of irradiation;3. Objectives of protection and safety; 4. Principles for practices;5. Principles for intervention; 6. Implementation principles; 7. Infra-structure for protection and safety; Definitions.

STI/PUB/1000 (24 pp.; 1996)E ISBN 92–0–105295–2Price: 160 Austrian schillings (€11.63)

RADIATION SAFETY OF GAMMA AND ELECTRON IRRADIATION FACILITIES Safety Series No. 107

Since the 1950s, gamma and electron beam facilities have been usedfor medical, industrial and research purposes, and their safety recordhas been very good. With the publication of this book, international,harmonized safety guidance is available for all those involved in thedesign, control and safe use of this type of irradiation facility.Subject areas such as the classification of irradiators, regulatorycontrol and special procedures are covered and the safety philoso-phy for all types of irradiators is explained.

Contents: 1. Introduction; 2. Types of irradiators; 3. Radiationsafety objectives; 4. Safety philosophy; 5. Design requirements;6. Regulatory control; 7. Responsibilities of the operating organiza-tion; 8. Responsibilities of designers and manufacturers, importersand suppliers, and constructors and installers; 9. The transport,loading and unloading of sources; 10. Special safety requirementsfor electron accelerator facilities; 11. Emergency response planning;References; Glossary.






SAFETY OF RADIATION SOURCES AND ➜NEWSECURITY OF RADIOACTIVE MATERIALSProceedings Series

Proceedings of an international conference jointly organized by theEC, IAEA, Interpol and WCO and held in Dijon, France,14–18 September 1998. The conference was the first of its kind


53

devoted to this subject and brought together radiation safety experts,regulators, and customs and police officers, in order to foster infor-mation exchange through a review of the state of the art and opendiscussions. The need was expressed for the formulation of interna-tional recommendations concerned with the effective operation ofnational systems for ensuring the safety of radiation sources and thesecurity of radioactive materials. These proceedings contain thekeynote address, the invited papers, summaries of discussions andsession summaries. Together with IAEA-TECDOC-1045, publishedin 1998 prior to the conference, they constitute the complete recordof the conference.

Contents: Opening session; The problem; Response from interna-tional organizations; The regulatory control of radiation sources,including systems for notification, authorization (registration andlicensing) and inspection; Safety assessment techniques applied toradiation sources: Design and technological measures, includingdefence in depth and good engineering practice; Managerialmeasures, including safety culture, human factors, quality assur-ance, qualified experts, training and education; Learning from oper-ational experience; International co-operation, including reportingsystems and databases; Verification of compliance, monitoring ofcompliance: Assessment of the effectiveness of nationalprogrammes for the safety of sources, including development ofperformance indicators; Measures to prevent breaches in the secu-rity of radioactive materials (from production to disposal), experi-ence with criminal acts involving radioactive materials; Detectionand identification techniques for illicitly trafficked radioactivematerials (I and II); Response to detected cases and seized radioac-tive materials, strengthening of the awareness, training, andexchange of information; Summaries by chairpersons of the techni-cal sessions.


THE RADIOLOGICAL ACCIDENT IN SOREQ


THE SAFE MANAGEMENT OF ➜NEWSOURCES OF RADIATION: PRINCIPLES AND STRATEGIES — A Report by the International Nuclear Safety Advisory GroupINSAG Series No. 11

This INSAG report deals with the general principles governing thesafety of all sources of radiation and with the application of theseprinciples. It seeks to demonstrate that, at the conceptual level, thedistinction traditionally made between nuclear safety and radiationprotection is not justified. This report is primarily intended for thenon-specialist who needs to take decisions about the safe manage-ment of sources of radiation and who wishes to gain a better under-standing of the approach followed in managing the safety of thesesources.

Contents: 1. Introduction; 2. Risk and risk management; 3. Thecontrol of radiation risk; 3. The management of specific sources ofradiation; 5. Summary and conclusions.



Transport of Radioactive Material

ADVISORY MATERIAL FOR THE IAEA REGULATIONS FOR THE SAFE TRANSPORT OF RADIOACTIVE MATERIAL(1985 Edition) — Third Edition (As Amended 1990): A Safety Guide Safety Series No. 37

This publication is an updated version of the Third Edition of theAdvisory Material for the IAEA Regulations for the Safe Transportof Radioactive Material (1985 Edition) and replaces all previouspublications of Safety Series No. 37. It includes the changes toSafety Series No. 37 contained in Supplement 1988 to the Regula-tions for the Safe Transport of Radioactive Material as well as somemodifications adopted by a Review Panel convened in Vienna inJuly 1989.

Contents: Section I. Introduction; Section II. General provisions;Section III. Activity and fissile material limits; Section IV. Prepara-tion, requirements and controls for shipment and for storage intransit; Section V. Requirements for radioactive materials and forpackagings and packages; Section VI. Test procedures; Section VII.Approval and administrative requirements; Appendix I: List of regu-latory documents of international and regional international organi-zations; Appendix II: Contamination control; Appendix III: Half-lifeand specific activity of radionuclides, and specific activity ofuranium and thorium; Appendix IV: Quality assurance in the safetransport of radioactive material; Appendix V: Guide for qualityassurance programme; Appendix VI: Example calculations forestablishing minimum segregation distance requirements; AppendixVII: Acceleration values and calculation methods for package tie-down forces; Appendix VIII: Example of a radiation protectionprogramme for exclusive use vessels; Appendix IX: Influence ofbrittle fracture on material integrity; Appendix X: Criticality safetyassessments.

STI/PUB/868 (206 pp., 8 figures; 1990) E ISBN 92–0–124090–2 C ISBN 92–0–500493–6 F out of print R out of print S ISBN 92–0–323291–5 Price: 620 Austrian schillings (€45.06)

CHARACTERIZATION OF RADIOACTIVE ➜NEWWASTE FORMS AND PACKAGESTechnical Reports Series No. 383

This report provides guidance on the determination and verificationof key waste characteristics and covers all parameters of wasteforms and packages needed to certify compliance with a specificdisposal scenario. It describes the different methods available for thecharacterization of chemical, physical and biological waste proper-ties as well as of properties related to radioactivity, indicating theadvantages and disadvantages of each individual method. The reportaddresses characterization of all types of radioactive waste exceptfor spent fuel intended for direct disposal.

Contents: 1. Introduction; 2. Categories of waste forms and pack-ages; 3. Basis for waste characterization; 4. Important parameters ofwaste packages; 5. Overview of the characterization process;6. Sampling; 7. Characteristics related to radioactivity; 8. Chemicalcharacteristics; 9. Physical characteristics; 10. Mechanical charac-teristics; 11. Thermal characteristics; 12. Biological properties;13. Conclusions.


R A D I A T I O N S O U R C E S A N D A C C E L E R A T O R S — T R A N S P O R T O F R A D I O A C T I V E M A T E R I A L

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COMPLIANCE ASSURANCE FOR THE SAFE TRANSPORT OF RADIOACTIVE MATERIALSafety Series No. 112

The 1985 Edition of the IAEA’s Regulations for the Safe Transportof Radioactive Material reinforced the requirement placed oncompetent authorities to establish compliance assuranceprogrammes that aim at ensuring that the Regulations are met inpractice. This book is intended to provide further guidance on devel-oping and implementing compliance assurance programmes to beused by competent authorities. It should also be useful to thosecompetent authorities with established programmes seeking greaterharmony in the international implementation of the Regulations.Additionally, it should assist the users of the Regulations in theirinteractions with competent authorities.

Contents: Section I. Introduction; Section II. Responsibilities andfunctions of the competent authority; Section III. Regulations andguides; Section IV. Compliance assurance; Section V. Approvals andapproval certificates; Section VI. International co-operation betweencompetent authorities concerning packages and shipments onforeign territory; Annex I: Example of the organization of a compli-ance assurance programme; Annex II: Information to be included inapplications for approvals; Annex III: Examples of approval certifi-cates issued by the competent authority; Annex IV: Model ofcompetent authority procedures for auditing a quality assuranceprogramme; Annex V: Example/model of a check list for auditing aquality assurance programme; Annex VI: Example/model of a checklist for inspecting transport documentation; Annex VII: Example/model of a check list for inspecting transport operations;Annex VIII: Example/model of a check list for inspecting packagemanufacture; Annex IX: Example/model of a check list for inspect-ing maintenance and servicing operations.


EMERGENCY RESPONSE PLANNING AND PREPAREDNESS FOR TRANSPORT ACCIDENTS INVOLVING RADIOACTIVE MATERIAL Safety Series No. 87

This safety guide is intended to expand the scope of andcomplement the available Agency literature in the areas of the trans-port of radioactive materials and emergency planning and prepared-ness for radiological emergencies. lt provides detailed guidance onhow to respond promptly to a transport accident involving radio-active materials in order to mitigate its consequences. Special atten-tion is given to such problems as how to identify the presence ofradioactive materials, their quantity and risk; how to assess the radi-ological consequences of an accident; and what measures should betaken in order to keep public exposures to a minimum and restorethe situation to normal as soon as possible.

Contents: Section I. Introduction; Section II. Transport regulations;Section III. Emergency response planning; Section IV. Conse-quences of transport accidents; Section V. Response to transportaccidents; Section Vl. Responsibilities for emergency planning andpreparedness; Section VII. Training, exercises and updating; SectionVIII. Public information; Appendix I: Markings, labels, placards anddocuments; Appendix II: Examples of response to transport acci-dents; Appendix III: Examples of some emergency response guidesand procedures; Bibliography.

STI/PUB/773 (116 pp., 12 figures; 1988) E ISBN 92–0–123088–5 F out of print R out of print S ISBN 92–0–323089–0 Price: 330 Austrian schillings (€23.98)

EXPLANATORY MATERIAL FOR THE IAEA REGULATIONS FOR THE SAFE TRANSPORT OF RADIOACTIVE MATERIAL (1985 Edition) — Second Edition (As Amended 1990) Safety Series No. 7

This publication is an updated version of the Second Edition of theExplanatory Material for the IAEA Regulations for the Safe Trans-port of Radioactive Material (1985 Edition) and replaces all previ-ous versions of Safety Series No. 7. It includes the changescontained in the Regulations for the Safe Transport of RadioactiveMaterial, 1985 Edition, Supplement 1988, as well as modificationsadopted by the Review Panel that was convened in July 1989.It explains the provisions of the Regulations with the aim of helpingto promote compliance and public acceptance.

Contents: Section I. Introduction; Section II. General provisions;Section III. Activity and fissile material limits; Section IV. Prepara-tion, requirements and controls for shipment and for storage intransit; Section V. Requirements for radioactive materials and forpackagings and packages; Section VI. Test procedures; Section VII.Approval and administrative requirements; Appendix I: The Qsystem for the calculation of A1 and A2 values; Appendix II: Deriva-tion of allowable release rates for type B packages; References.

STI/PUB/867 (124 pp., 5 figures; 1990) E ISBN 92–0–123990–4 C ISBN 92–0–500393–X F ISBN 92–0–200392–0R out of print S ISBN 92–0–323191–9 Price: 400 Austrian schillings (€29.07)

HYPERTRANS! A Hypertext Guide to the IAEA Transport Regulations,Safety Series Nos 6, 7, 37 and 80

HyperTrans! is a hypertext software guide to IAEA Safety SeriesNos 6, 7, 37 and 80. It contains their full texts and links all internalreference within each document as well as the reference betweendocuments. The text can be easily accessed either by searching andfinding all occurrences in a document or by using one or morekeywords connected by parameters. The use of HyperTrans!requires: (a) a 386 (or later) microprocessor running DOS; (b) aminimum 4 MB of free space on the hard disk; and (c) a VGAmonitor.

STI/DAT/1 (1 manual, 1 diskette 3.50”, 2 diskettes 5.25”; 1994) ISBN 92–0–102794–X Price: 2200 Austrian schillings (€159.88)

QUALITY ASSURANCE FOR THE SAFE TRANSPORT OF RADIOACTIVE MATERIALSafety Series No. 113

This publication provides guidance and gives detailed advice onmethods and practical examples to develop quality assurance (QA)programmes for the safe transport of radioactive material. It furtherpromotes a flexible approach to the development of a QAprogramme and may be used to prepare such a programme for aspecific application by selection of appropriate features.

Contents: 1. Introduction; 2. Development of a quality assuranceprogramme; 3. Quality assurance standards; 4. Elements of a qualityassurance programme; Appendix: Graded approach; Annex I: Twocomparative examples of quality assurance programme develop-ment; Annex II: References to examples of quality assurance stan-dards; Annex III: Example of a documented quality assuranceprogramme description for an infrequent consignor; Annex IV:Example of a documented quality assurance programme description


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for an infrequent carrier; Annex V: Example of a document controlprocedure for a small organization; Annex VI: Example of a docu-ment control procedure for a complex organization; Annex VII:Example of an internal audit procedure in a small organization;Annex VIII: Example of a flask maintenance procedure in acomplex organization; Annex IX: Examples of poor interfacecontrol.


REGULATIONS FOR THE SAFE TRANSPORT OF RADIOACTIVE MATERIAL — 1985 Edition(As Amended 1990) Safety Series No. 6

This publication is an updated version of the 1985 Edition of theTransport Regulations and replaces all previous publications ofIAEA Safety Series No. 6. It includes the Supplements 1986 and1988 to the Regulations and the minor changes adopted by thereview Panel meeting in Vienna in July 1989.

This edition of the Regulations serves as the basis for regulatoryrequirements in international modal regulatory documents and willcontinue to do so until the end of 2001 when the 1996 Edition of theRegulations (TS-R-1 (ST-1, Revised)) will serve as that basis.

Contents: Section I. Introduction; Section II. General provisions;Section III. Activity and fissile material limits; Section IV. Prepara-tion, requirements and controls for shipment and for storage intransit; Section V. Requirements for radioactive materials and forpackagings and packages; Section VI. Test procedures; Section VII.Approval and administrative requirements; Appendix I: Excerptsfrom list of United Nations numbers, proper shipping name anddescription and subsidiary risks; Appendix II: Conversion factorsand prefixes.

STI/PUB/866 (112 pp., 6 figures; 1990)E ISBN 92–0–123890–8C ISBN 92–0–500193–7F out of printR out of printS ISBN 92–0–323091–2Price: 380 Austrian schillings (€27.62)

S A F E T Y S T A N D A R D S S E R I E S

The IAEA Safety Standards Series comprises publications of a regu-latory nature covering nuclear safety, radiation protection, radio-active waste management, the transport of radioactive materials, thesafety of nuclear fuel cycle facilities and quality assurance. Thesepublications are issued under the terms of Article III of the Agency’sStatute, which authorizes the Agency to establish standards of safetyfor protection against ionizing radiation. The Safety StandardsSeries supersedes the Safety Series, in which over 200 publicationswere issued. Safety Standards Series publications are categorizedinto:

• Safety Fundamentals (F; blue lettering), stating basic objec-tives, concepts and principles of safety and protection;

• Safety Requirements (R; red lettering), establishing therequirements that must be fulfilled to ensure safety forparticular activities or applications; and

• Safety Guides (G; green lettering), recommending actions,conditions or procedures for complying with these safetyrequirements.

For numbering purposes, the Safety Standards Series is subdividedinto the areas of nuclear safety (NS), radiation safety (RS), transportsafety (TS) and waste safety (WS), and also general safety (GS; thatis, of relevance in two or more of the four areas).

S A F E T R A N S P O R T

REGULATIONS FOR THE SAFE TRANSPORT ➜NEWOF RADIOACTIVE MATERIAL — 1996 Edition (Revised): Safety RequirementsSafety Standards Series No. TS-R-1 (ST-1, Revised)

This publication, Safety Standards Series No. TS-R-1, is an updatedversion of Safety Standards Series No. ST-1, which was a revisedversion of Safety Series No. 6 superseding all previous edition. Italso includes the revision of Safety Series No. 80, Schedules ofRequirements for the Transport of Specified Types of RadioactiveMaterial Consignments (As Amended in 1990). These Regulations,first published in 1961, establish standards of safety with thepurpose of providing an acceptable level of control of the radiation,criticality and thermal hazards to persons, property and the environ-ment that are associated with the transport of radioactive material.Through the worldwide adoption of these regulations for all modesof transport, a very high standard of safety in the transport ofradioactive material has been achieved.

Contents: Section I: Introduction; Section II: Definitions;Section III: General provisions; Section IV: Activity limits andmaterial restrictions; Section V: Requirements and controls fortransport; Section VI: Requirements for radioactive materials andfor packagings and packages; Section VII: Test procedures; SectionVIII: Approval and administrative requirements; Reference; Sched-ules of Requirements for the Transport of Specified Types ofRadioactive Material Consignments; Annex I: Summary of approvaland prior notification requirements; Annex II: Conversion factorsand prefixes.

STI/PUB/1098 (220 pp., 7 figures; 2000)E ISBN 92–0–100500–8F ISBN 92–0–204497–X Safety Standards Series No. ST-1 isR ISBN 92–0–401598–5 still valid. Changes introduced intoS ISBN 92–0–302697–5 Safety Standards Series No. TS-R-1

(ST-1, Revised) will be reflected in anerrata sheet included in the publication.

Price: 200 Austrian schillings (€14.53)

SCHEDULES OF REQUIREMENTS FOR THE TRANSPORT OF SPECIFIED TYPES OF RADIOACTIVE MATERIAL CONSIGNMENTS (As Amended 1990) — Companion Document to Safety Series No. 6Safety Series No. 80

This publication replaces the previous issue of Safety Series No. 80.It includes the changes to Safety Series No. 80 contained in Supple-ment 1988 to the Regulations for the Safe Transport of RadioactiveMaterial as well a some modifications adopted by the Review Panelmeeting held in Vienna in July 1990.

Contents: Schedule 1: Limited quantities of radioactive material inexpected packages; Schedule 2: Instruments in articles in expectedpackages; Schedule 3: Articles manufactured from natural uranium,depleted uranium or natural thorium as excepted packages; Sched-ule 4: Empty packagings as excepted packages; Schedule 5: Lowspecific activity material (LSA-1); Schedule 6: Low specific activ-ity material (LSA-II); Schedule 7: Low specific activity material(LSA-III); Schedule 8: Surface contaminated objects (SCO-I andSCO-II); Schedule 9: Material in Type A packages; Schedule

}

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10: Material in Type B(U) packages; Schedule 11: Material in TypeB(M) packages; Schedule 12: Fissile material; Schedule 13: Mater-ial transported under special arrangement; Annex I: Other provi-sions relating to Schedules 1–13; Annex II: Summary of approvaland prior notification requirements; Annex III: Transport indexlimits for freight containers and conveyances.

STI/PUB/869 (108 pp., 1990)E ISBN 92–0–124190–9C ISBN 92–0–500293–3F out of printR ISBN 92–0–423091–6S ISBN 92–0–323391–1Price: 360 Austrian schillings (€26.16)

Waste Repositories

CONTAINERS FOR PACKAGING OF SOLID AND INTERMEDIATE LEVEL RADIOACTIVE WASTESTechnical Reports Series No. 355

This report aims to review the main requirements for wastecontainers and to provide advice on the design, fabrication,qualification tests and handling of the different types of containersused in the management of low and intermediate level solid radio-active wastes. It contains the requirements that have to be met in thecontainer design in order to comply with the waste package accep-tance requirements established by the regulatory authorities for thehandling, storage, transport and disposal of radioactive waste. Itfurther highlights the importance of international standardization forwaste container requirements, which would facilitate the use ofcommon handling systems and allow operating experience andperformance data to be readily interchangeable.

Contents: 1. Introduction; 2. Role of the container in waste manage-ment; 3. Container design requirements; 4. Materials for containers;5. Cost considerations; 6. Quality assurance and control; 7. Quali-fication tests; 8. Conclusions and recommendations; Appendix I:Examples of containers; Appendix II: Corrosion assessments ofmetallic containers; Appendix III: Specification of a test for thermalcycling resistance in France; Appendix IV: A qualification proce-dure for fibre reinforced concrete containers in France.


GEOLOGICAL DISPOSAL OF SPENT FUEL AND HIGH LEVEL AND ALPHA BEARING WASTESProceedings Series

Proceedings of a symposium organized jointly with CEC andOECD/NEA, Antwerp, Belgium, 19–23 October 1992. The purposeof the symposium was to review the progress being made in nationaland international programmes towards the demonstration of safedisposal of radioactive wastes. The technical presentationsaddressed disposal in all the principal geological media currentlyunder consideration: clay, crystalline rock, salt and volcanic tuff.The programmes described ranged from national screening surveyson a broad, regional scale to detailed site specific investigations inunderground research laboratories.

Contents: Keynote address; Programmes of international organiza-tions; Site characterization programmes and methods; Repositorydesign concepts, construction techniques and engineered barrierdesign; Characterization and acceptance of high level and alphabearing wastes; Repository concepts for direct disposal of spentfuel; Developing, testing and validating repository performance

assessment models; National and international programmes; Posterpresentations.


GUIDANCE FOR REGULATION OF UNDERGROUND REPOSITORIES FOR DISPOSAL OF RADIOACTIVE WASTES Safety Series No. 96

Most countries regulate the disposal of radioactive wastes by a regu-latory body whose purpose is to review and analyse the safety of allstages of the disposal programme. This regulatory function may beperformed either by a single national authority or a system ofauthorities. This publication should be used as a guide to developingregulatory requirements for licensing waste disposal facilities. lt isan update of IAEA Safety Series No. 51.

Contents: 1. Introduction; 2. Scope; 3. Basic considerations;4. Stages in the development of a repository; 5. Regulatoryfunctions; 6. Repository siting and design; 7. Construction andcommissioning; 8. Operation; 9. Shutdown; 10. Subsequent controland future use of the site.


HYDROGEOLOGICAL INVESTIGATION ➜NEWOF SITES FOR THE GEOLOGICAL DISPOSAL OF RADIOACTIVE WASTETechnical Reports Series No. 391

This report, which has been prepared as part of the IAEAprogramme on radioactive waste disposal, discusses the approachesused in the hydrogeological investigation of repository sites. It isbased on experience gained in Member States on those rock typesconsidered as having the potential to host a repository.

Contents: 1. Introduction; 2. Geological disposal of radioactivewaste; 3. Function of the geological barrier in a disposal system; 4.Focusing hydrogeological investigations; 5. Hydrogeological issuesin disposal systems; 6. Approaches to characterization of the hydro-geological system; 7. Summary.


NATURAL ANALOGUES IN PERFORMANCE ASSESSMENTS FOR THE DISPOSAL OF LONG LIVED RADIOACTIVE WASTES Technical Reports Series No. 304

A unique and scientifically most difficult aspect of predictive safetyanalysis of repositories for long lived wastes is the extrapolation ofshort term field and laboratory data to the long periods of timerequired by regulatory agencies for performance assessment.Natural analogues may be the only way of obtaining data on thecumulative effect of the migration of radionuclides over the time-scales of interest. This report briefly summarizes the state of the artin this field for technical specialists and may also serve as an intro-duction to the subject for managers.

Contents: 1. Introduction; 2. Natural analogues in performanceassessment; 3. Potential roles of analogues in performance assess-ments; 4. Analogues: Their applications and limitations; 5. Discus-


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sion of the quantitative and qualitative roles of analogues; 6. Conclu-sions and recommendations; Appendix A: Use of natural and archae-ological analogues in performance assessment of the KBS-3 coppercanister; Appendix B: The Cigar Lake uranium deposit: An analoguefor nuclear fuel waste disposal; Appendix C: Uranium isotope studiescombined with groundwater dating as a natural analogue.


SAFETY PRINCIPLES AND TECHNICAL CRITERIA FOR THE UNDERGROUND DISPOSAL OF HIGH LEVEL RADIOACTIVE WASTES Safety Series No. 99

This report is to provide basic guidance on protection of humans andthe environment from the hazards associated with deep geologicaldisposal of high level radioactive wastes. It reflects the need forinternationally harmonized criteria. It sets out a basic safety philos-ophy for use in planning such disposals, the main objective being theisolation of the radioactive wastes from the human environment forconsiderable periods of time. The safety principles contained in thisbook are generally consistent with the recent recommendations ofthe International Commission on Radiological Protection (ICRP)and the Nuclear Energy Agency of the OECD (OECD/NEA).

Contents: 1. Introduction; 2. Definitions; 3. Safety principles;4. Technical criteria; 5. Assurance of compliance with the safetyobjectives; 6. Other considerations.


SEALING OF UNDERGROUND REPOSITORIES FOR RADIOACTIVE WASTES Technical Reports Series No. 319

For high level and alpha bearing radioactive wastes, the disposalconcept most generally agreed upon is the emplacement of the condi-tioned waste in deep underground repositories in stable geologicalformations. The report reflects the general consensus that long livedradioactive wastes can be isolated safely from the human environmentin such repositories located in deep geological formations. One of themost important tasks in the development of underground disposalsystems is the plugging of boreholes and the sealing of shafts exca-vated for either exploratory or operational purposes. Several countrieshave outlined proposals and identified geological formations fordetailed examination as potential host media for waste repositories.

Contents: 1. Introduction and scope; 2. Background information;3. Performance specifications; 4. Materials and methods;5. Longevity; 6. Design factors; 7. Design of sealing systems;8. Performance testing; References; Glossary.


SITING, DESIGN AND CONSTRUCTION OF UNDERGROUNDREPOSITORIES FOR RADIOACTIVE WASTES Proceedings Series

Proceedings of a symposium, Hannover, Germany, 3–7 March 1986.The purpose was to review advances made in the area of siting,

design and construction of underground repositories for radioactivewastes and to consider developments of future importance. Forty-nine papers were presented, covering general approaches and regu-latory aspects, disposal in shallow ground and rock cavities, disposalin deep geological formations and safety assessments.

Contents: Keynote address: Are we ready to construct and operatean underground repository? General approaches and regulatoryaspects; Disposal in shallow ground and rock cavities; Disposal indeep formations: Investigations on sites; Disposal in deep forma-tions: Repository designs; Safety assessment; PaneI: Performanceand safety assessments and their interactions with field investiga-tions of deep geological repositories; Overview of symposium.


Radiation Protection

ACCIDENTAL OVEREXPOSURE ➜NEWOF RADIOTHERAPY PATIENTS IN SAN JOSÉ, COSTA RICA


ASSESSMENT OF DOSES TO THE ➜NEWPUBLIC FROM INGESTED RADIONUCLIDESSafety Reports Series No. 14

This Safety Report provides practical information as a basis for radi-ation protection of the public in the event of accidental releases ofradionuclides to the environment, transfer from environmentalmedia into foodstuffs and ingestion by members of the public. Itoffers the scientific basis for the values of committed effective dosesper unit intake of radionuclides via ingestion and their application,providing the information necessary to assess the radiological impli-cations, in terms of doses to population groups, of the measuredconcentrations of radionuclides in foodstuffs independent of thesource of exposure.

Contents: 1. Introduction; 2. Entry of radionuclides into the foodchain; 3. Food consumption and dose assessment; 4. Dosecoefficients for ingested radionuclides; 5. Dose assessment frommeasurements on individuals; Annex I. Food consumption in differ-ent countries; Annex II. Committed equivalent tissue doses per unitactivity ingested by adults; Annex III. Activity in total body, thyroidand excreta after acute and chronic intake by ingestion of selectedradionuclides.


COMPENDIUM OF NEUTRON SPECTRA AND DETECTORRESPONSES FOR RADIATION PROTECTION PURPOSES Technical Reports Series No. 318

A wide variety of radiation dosimeters and survey instruments areused to monitor exposure to neutrons. To establish an adequateneutron monitoring programme and to evaluate dosimetry resultsproperly, it is important to know both the energy distribution of theneutrons encountered and the energy dependent response of themeasuring devices. It is also important for calibration to use neutronfields whose spectra are appropriate for the particular application.This compendium includes a collection of neutron spectra encoun-tered in various occupational environments and the spectra of

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calibration neutron sources. It also gives the response functions ofvarious neutron dosimeters and survey instruments. Finally, itincludes the calculated energy responses for each of the detectorsand spectra given.

Contents: Chapter 1: Introduction; Chapter 2: Dosimetric quanti-ties; Chapter 3: Dosimeters and survey instrument response func-tions; Chapter 4. Calibration neutron spectra; Chapter 5. Operationalspectra; Chapter 6. Monoenergetic neutrons incident on ellipticalphantom.

If you are interested in obtaining the free diskette on the neutronfluence to dose conversion factors, detector responses and spectratabulated, please mention this in the order form.


DERIVED INTERVENTION LEVELS FOR APPLICATION IN CONTROLLING RADIATION DOSES TO THE PUBLIC IN THE EVENT OF A NUCLEAR ACCIDENT OR RADIOLOGICAL EMERGENCY — Principles, Procedures and Data Safety Series No. 81

This publication provides practical support to the guidancecontained in IAEA Safety Series No. 72, Principles for EstablishingIntervention Levels for the Protection of the Public in the Event of aNuclear Accident or Radiological Emergency. In the event of anuclear accident or radiological emergency there is a need to deter-mine the levels of projected dose at which it may be necessary tointroduce relevant protective measures. However, more practicalquantities are needed for the comparison of measurement resultsmade in environmental materials and in foodstuffs. These derivedintervention levels (DlLs) need to be determined for the radionu-clides of potential radiological importance. This report gives guid-ance in elaborating the principles, procedures and methodologiesrelevant to the evaluation of DILs.

Contents: Introduction; Intervention levels and principles underly-ing their estimation; Procedures for establishing derived interven-tion levels for exposure due to a single radionuclide and single expo-sure pathway; Estimation of derived intervention levels and theirpractical application; Annex 1: Derived intervention levels forselected nuclides and exposure pathways; Annex 2: Definition ofsymbols used.

STI/PUB/751 (105 pp., 3 figures; 1986) E out of print F out of print R ISBN 92–0–424189–6 S ISBN 92–0–323288–5 Price: 360 Austrian schillings (€26.16)

DESIGN ASPECTS OF RADIATION PROTECTION FOR NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-D9

(See under Nuclear Power Plants, NUSS programme, p. 39)

DIAGNOSIS AND TREATMENT ➜NEWOF RADIATION INJURIESSafety Reports Series No. 2


DIRECT METHODS FOR MEASURING ➜NEWRADIONUCLIDES IN THE HUMAN BODY: A Safety PracticeSafety Series No. 114

This Safety Practice provides information on the establishment andoperation of facilities for the measurement of body activity by directmethods, both in general application and in a range of specific situ-ations. Emphasis is placed on measurements of body radioactivitymade in programmes of internal dosimetry for occupationallyexposed persons, or in investigations following incidents. Assess-ments of larger groups following general contamination of the envi-ronment are also addressed.

Contents: 1. Introduction; 2. Conditions for using direct methodsfor measuring radionuclides in the human body; 3. Techniques ofinvestigation; 4. Analysis of data from measurements; 5. Practicaldetails; References; Annex I. Indices of statistical significance andsensitivity; Annex II. Use of semiconductor detector in the investi-gation of internal contamination with complex mixtures of radio-nuclides; Annex III. Investigation of whole body 137Cs with mobileequipment; Annex IV. Investigation of internal contamination with60Co; Annex V. Estimation of whole body 137Cs with a scanningarray of NaI(T1) detectors installed for assessment of fission andactivation products; Annex VI. Assessment of 125I and 131I in thethyroid; Annex VII. Investigation of internal contamination with241Am; Annex VIII. Assessment of uranium in the lungs.


EFFECTS OF IONIZING RADIATION ON PLANTS AND ANIMALS AT LEVELS IMPLIED BY CURRENT RADIATION PROTECTION STANDARDS Technical Reports Series No. 332

Releases of waste gases and liquids into the environment from facil-ities using radioactive materials are controlled so that people livingin the vicinity are adequately protected from exposure to ionizingradiations. It is implicitly assumed that protecting humans will alsoprotect the environment in which they live. Although this assump-tion has never been formally defended, neither has it been seriouslychallenged. This report examines the validity of the assumption forthe case of radioactive releases to the terrestrial and freshwater envi-ronments and also for solid waste disposal underground.

Contents: 1. Introduction; 2. Summary of the available informationon the effects of ionizing radiation on populations; 3. Estimated doseto plants and animals under current radiation protection standards; 4.Summary and conclusions; References.


ENVIRONMENTAL IMPACT OF RADIOACTIVE RELEASES Proceedings Series

Proceedings of a symposium, Vienna, 8–12 May 1995. This was thefirst major IAEA meeting for more than a decade to deal specificallywith the transfer of radionuclides in the environment. Its purposewas to review the information that has become available in recentyears, notably as a result of the Chernobyl accident but also gainedfrom studies of the discharges from civil and military nuclear facil-ities in the early nuclear age. This information has been used forimproving the reliability of environmental model predictions, andthe main results of the IAEA/CEC programme on Validation of


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Environmental Model Predictions (VAMP) were presented. Inaddition, progress in the IAEA programme on the InternationalArctic Seas Assessment Project (IASAP) was summarized.

Contents: Global impact assessments; New roles for environmentalmonitoring; Radionuclide releases to the atmosphere; Radionuclidereleases to the aquatic environment; Radionuclides in the terrestrialenvironment; Radionuclide transfer in the freshwater environment;Environmental model testing; Radiological impact assessment;Environmental remediation; Topical discussions.


EXTENSION OF THE PRINCIPLES OF RADIATION PROTECTION TO SOURCES OF POTENTIAL EXPOSURE Safety Series No. 104

The principles of radiation protection recommended by the Interna-tional Commission on Radiological Protection for the normal oper-ation of a radiation source constitute a dose limitation system thathas three components: namely, the justification of a practice, theoptimization of radiation protection and the limitation of individualdoses. This report describes how the application of these principlesmay be extended to unexpected or accidental situations by changingfrom the dose based system of radiation protection to a unifiedapproach within a probabilistic framework.

Contents: Summary; 1. Introduction; 2. Basic principles; 3. Con-cepts and quantities; 4. Measures of societal risk; 5. Justification;6. Optimization of potential exposures; 7. Limitation of individualrisk; 8. Conclusions.


GUIDELINES ON CALIBRATION OF NEUTRON MEASURING DEVICES Technical Reports Series No. 285

The majority of the existing Secondary Standard Dosimetry Labora-tories (SSDLs) were established primarily to work with X rays andgamma rays. Neutron sources are, however, increasingly beingapplied in industrial processes, research, nuclear power develop-ment, and radiation biology and medicine. This publication dealsprimarily with methods of applying radioactive neutron sources forcalibration of instrumentation and gives an indication of the space,manpower and facilities needed to fulfil the minimum requirementsof a calibration laboratory for neutron work. Its intention is to serveas a guide for centres about to start on neutron dosimetry standard-ization and calibration.

Contents: 1. Introduction; 2. Concepts of dosimetry and calibration;3. Types of calibration and test measurement; 4. Sources, equipmentand facilities; 5. Procedures and methods; 6. Calibration of beamdosimeters; 7. Reports and records; Appendix I: Basic quantities andunits; Appendix II: Glossary; Apendix III: Neutron sources;Appendix IV: Fluence to dose equivalent conversion functions;Appendix V: List of symbols; References.


HEALTH SURVEILLANCE OF PERSONS ➜NEWOCCUPATIONALLY EXPOSED TO IONIZING RADIATION: GUIDANCE FOR OCCUPATIONAL PHYSICIANSSafety Reports Series No. 5

This Safety Report specifies features of work under radiation condi-tions, the general rules of radiological protection for occupationalexposure and the organization of the medical surveillance ofworkers occupationally exposed to radiation. It supersedes IAEASafety Series No. 83, Radiation Protection in Occupational Health:Manual for Occupational Physicians (1987).

Contents: 1. Introduction; 2. Modes of exposure; 3. Protectionagainst occupational exposure; 4. Application of radiological protec-tion principles; 5. Health surveillance and medical records;6. Medical management of accidentally exposed workers; Refer-ences; Annex: Health effects of ionizing radiation; Glossary.

STI/PUB/1056 (37 pp., 1 figure; 1998)E ISBN 92–0–103898–4Price: 200 Austrian schillings (€14.53)

INTERNATIONAL BASIC SAFETY STANDARDS ➜NEWFOR PROTECTION AGAINST IONIZING RADIATION AND FOR THE SAFETY OF RADIATION SOURCES: A Safety Standard Safety Series No. 115

Jointly sponsored by FAO, IAEA, ILO, OECD/NEA, PAHO andWHO

These Standards are based on the latest assessments of the biologicaleffects of irradiation made by the United Nations Scientific Commit-tee on the Effects of Atomic Radiation, and on the recommendationsof the International Commission on Radiological Protection and theInternational Nuclear Safety Advisory Group. The Standards repre-sent an international consensus on qualitative and quantitativerequirements for protection and safety for: planned practices such asnuclear power generation and the use of radiation and radioactivematerials in medicine and industry; intervention in existing situationssuch as chronic exposure to natural sources of radiation or exposurefollowing an accident; control of radiation sources, including notifi-cation and authorization, and criteria for exemption. Consensus guid-ance is also given on: occupational radiaton protection; protection ofpatients in radiography, fluoroscopy, computer tomography,mammography and nuclear medicine; protection of members of thepublic from exposure to radioactive materials released to the envi-ronment; prevention of incidents giving rise to potential exposures;and intervention in a radiological emergency.

Contents: Preamble: Principles and fundamental objectives; Princi-pal requirements: 1. General requirements; 2. Requirements for prac-tices; 3. Requirements for intervention. Appendices: Detailedrequirements: Occupational exposure; Medical exposure; Publicexposure; Potential exposure: Safety of sources; Emergency expo-sure situations; Chronic exposure situations; Schedules: Exemptions;Dose limits; Guidance levels of dose, dose rate and activity formedical exposure; Dose levels at which intervention is expected to beundertaken under any circumstances; Guidelines for interventionlevels and action levels in emergency exposure situations; Guide-lines for action levels in chronic exposure situations; Glossary; Index.

STI/PUB/996 (353 pp.; 1996) E ISBN 92–0–104295–7A ISBN 92–0–104195–7C ISBN 92–0–505196–9F ISBN 92–0–204497–XR ISBN 92–0–401598–7S ISBN 92–0–300397–5Price: 1080 Austrian schillings (€78.49)

R A D I A T I O N P R O T E C T I O N

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THE BASIC SAFETY STANDARDS ➜NEWON DISKETTESafety Series No. 115

This Windows based software program contains the text and datafrom the English printed version of Safety Series No. 115. The userof the program should be generally familiar with the organizationand content of the Standards. The program enables the user to searchfor and retrieve any topic directly through the ‘Contents’ tree, withaccess based on keyword searches, a subject index or cross-refer-encing. The definitions of the main concepts can be found in the‘Glossary’ list. Text may be printed directly, or used in the develop-ment of other documents through the normal ‘copy and paste’Windows feature. The software requires an IBM compatiblePersonal Computer with an 80386 processor or better, more than 4MB internal memory, at least 4 MB free memory on hard disk andWindows 3.11 or Windows ‘95.

Contents: Preamble: Principles and fundamental objectives; Princi-pal requirements: 1. General requirements; 2. Requirements forpractices; 3. Requirements for intervention. Appendices: Detailedrequirements: Occupational exposure; Medical exposure; Publicexposure; Potential exposure: safety of sources; Emergency expo-sure situations; Chronic exposure situations; Schedules: Exemp-tions; Dose limits; Guidance levels of dose, dose rate and activity formedical exposure; Dose levels at which intervention is expected tobe undertaken under any circumstances; Guidelines for interventionlevels and action levels in emergency exposure situations; Guide-lines for action levels in chronic exposure situations. Glossary;Index.

STI/DAT/2 (1997)ISBN 92–0–100997–6Price: single user: 300 Austrian schillings (€21.80)

multiuser: 600 Austrian schillings (€43.60)

INTERVENTION CRITERIA IN A NUCLEAR OR RADIATION EMERGENCY Safety Series No. 109

This Safety Guide represents an international consensus and under-standing on principles for intervention and numerical values forgeneric intervention levels. It became clear during the ChernobylProject that there was a need for clarification of the internationalguidance on intervention and, moreover, for a simple set of inter-nally consistent intervention levels having some generic applicationinternationally. The recommendations in this publication are thebasis for the standards and numerical guidance related to interven-tion that are contained in the International Basic Safety Standardsfor Protection against Ionizing Radiation and for the Safety of Radi-ation Sources (jointly sponsored by FAO, IAEA, ILO, OECD/NEA,PAHO and WHO).

Contents: 1. Introduction; Part I: Background and principles;Part II: Application to members of the public; Part III: Applicationto workers; Annex I: Technical analysis to assist in the selection ofgeneric intervention levels; Annex II: Application of generic inter-vention levels; Annex III: Risk perspectives.

STI/PUB/900 (117 pp., 16 figures; 1994) E ISBN 92–0–103094–0 F ISBN 92–0–201699–2R ISBN 92–0–401698–1S ISBN 92–0–303396–3 Price: 400 Austrian schillings (€29.07)

LOW DOSES OF IONIZING RADIATION: ➜NEWBIOLOGICAL EFFECTS AND REGULATORY CONTROL: Invited Papers and DiscussionsProceedings Series

Proceedings of a conference jointly organized with WHO, in co-operation with UNSCEAR, Seville, Spain, 17–21 November 1997.The purpose of the conference was to foster information exchangeon the health effects of low doses of ionizing radiation, the regula-tory approach to the control of low level radiation exposure, and theconnection between these matters and the so-called linear, no thresh-old assumption concerning the effects of low doses.

Contents: Opening session; Reports form international organiza-tions on biological effects of ionizing radiation; Reports on relatedinternational conferences; Molecular mechanisms of radiationeffects: Point and clastogenic mutations (Forum 1); Adaptiveresponses: Enhanced repair and apoptosis (Forum 2); Multistageprocesses of radiation induced malignancies; Mechanisms of initia-tion, promotion and progression (Forum 3); Hereditary effects(Forum 4); Epidemiological evidence (Forum 5); Radiobiologicalissues in the application of epidemiological evidence (Forum 6);Effects of low doses on human health: Radiation risk estimates(Forum 7); From the scientific evidence to radiation protection(Special session); Control measures for practices causing exposure(Forum 8); Reduction of existing doses by intervention (Forum 9);Chronic exposure situations: Radiological criteria for restoration ofland (Forum 10); Regulatory control and scientific research;Summary session; Closing session.




Contents: 1. Introduction; 2. Pathways and samples of interest;3. Radionuclides of interest; 4. Requirements for laboratories,equipment and personnel; 5. Collection and preparation of samples;6. Analytical methods; 7. Analytical quality control; References:Sections 1–7; Bibliography: Sections 1–7; Annex I: Method fordetermining gamma emitters; Annex II: Methods for radiochemicalanalysis of strontium; Annex III: Method for radiochemical analysisof tritium; Annex IV: Methods for radiochemical analysis of pluto-nium, americium and curium; Annex V: Units, prefixes and symbols;Annex VI: Nuclear accident scenarios; Annex VII: Radionuclidedata; Annex VIII: Grass sample collection; Annex IX: Gamma spec-trometric systems; Annex X: Potential suppliers of calibrationsources and reference materials.


MEDICAL HANDLING OF ACCIDENTALLY EXPOSED INDIVIDUALS Safety Series No. 88

This manual is the first of three Safety Series publications dealingwith assessment and treatment of over-exposures which will


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constitute an articulated system of documents covering all aspects ofdiagnosis, prognosis and treatment. It establishes a set of generalcriteria and recommendations to aid specialists involved in themedical handling of overexposed persons.

Contents: 1. Introduction; 2. Accidental external exposure;3. Procedures to follow in the event of an external overexposure;4. Radioactive contamination; 5. Organization, planning and train-ing; 6. Medical advice following accidental occupational exposures;Appendix 1: Internationally available radiation assistanceprogrammes; Appendix 2: Centres for treatment of accidentallyexposed individuals and for training; Appendix 3: Specimen of acci-dent report form; Appendix 4: Early clinical symptoms associatedwith partial body exposure; Appendix 5: Definitions.


METHODS FOR REDUCING OCCUPATIONAL EXPOSURES DURING THE DECOMMISSIONING OF NUCLEAR FACILITIES Technical Reports Series No. 278

This is a review of methods for reducing occupational exposuresduring the decommissioning of nuclear facilities. The report focuseson water cooled nuclear power plants but, in addition, other majornuclear facilities are briefly discussed in this regard.

Contents: 1. Introduction; 2. Scope; 3. Basic considerations;4. Methods for reducing occupational exposures; 5. Health physicsprogramme; 6. Optimization of exposure reduction techniques; 7.Effects on waste management; 8. Relevant experience; 9. Applica-tion to other facilities; 10. Summary.

STI/DOC/10/278 (42 pp.; 1987) ISBN 92–0–125387–7 Price: 160 Austrian schillings (€11.63)

ONE DECADE AFTER CHERNOBYL — ➜NEWSumming up the Consequences of the AccidentProceedings Series

(see under Accident Response, p. 70)

OPERATIONAL RADIATION PROTECTION: A GUIDE TO OPTIMIZATION Safety Series No. 101

The purpose of this publication is to provide practical guidance onthe application of the dose limitation system contained in the BasicSafety Standards for Radiation Protection, Safety Series No. 9, tooperational situations both in large nuclear installations and in muchsmaller facilities, with special reference to the principles of opti-mization. It supersedes Safety Series No. 13.

Contents: 1. Introduction; 2. Dose limitation system; 3. Optimiza-tion and its practical application to operational radiation protection;4. Major elements of an effective operational radiation protectionprogramme; Annex I: Review of selected parts of the Basic SafetyStandards with special reference to operational radiation protection;Annex II: Optimization of radiation protection; Annex III: Tech-

niques for the systematic appraisal of operational radiation protec-tion programmes.


OPTIMIZATION OF RADIATION PROTECTION Proceedings Series

Proceedings of a symposium jointly organized with OECD/NEA,Vienna, 10–14 March 1986. The purpose of the symposium was todiscuss whether the optimization principle was being successfullyapplied in practical radiation protection, to illustrate the methodolo-gies developed and to appraise the role of optimization in radiationprotection by identifying its potential and its limitations.

Contents: The role of radiation protection; Application of theprinciple of radiation protection; Methods and techniques in theoptimization of radiation protection; Closing session.


PRINCIPLES FOR LIMITING RELEASES OF RADIOACTIVE EFFLUENTS INTO THE ENVIRONMENT: A Safety Guide Safety Series No. 77

This publication is a complete revision of Safety Series No. 45, Prin-ciples for Establishing Limits for the Release of Radioactive Mate-rials into the Environment (1978), and its Annex (1982). It isconcerned with the subject of limiting releases of radioactive efflu-ents during normal, controlled operations of nuclear installations. Itdoes not deal with releases during accidents where it is only possi-ble to limit exposures by intervention. In practice, a choice must bemade between releasing radioactive materials directly from aninstallation, storing them, treating and disposing of them by somemeans, or a combination of these methods.

Contents: Concepts and quantities; Assessment of individual dose;Assessment of collective dose; Setting release limits; References;Explanation of terms.

STI/PUB/728 (32 pp., 3 figures; 1986) E out of printC ISBN 92–0–523690–X F ISBN 92–0–223587–2 R ISBN 92–0–423089–4 S ISBN 92–0–323387–3 Price: 150 Austrian schillings (€10.90)

PRINCIPLES FOR THE EXEMPTION OF RADIATION SOURCES AND PRACTICES FROM REGULATORY CONTROL Safety Series No. 89

The need for a consistent international approach to exclusion andexemption of radiation sources and practices from regulatory controlhas become increasingly evident, especially for sources which maybe transported from one country to another, such as consumer prod-ucts containing very small amounts of radioactive material. Thissafety guide represents a first international consensus on the subjectof exemption principles. It recommends a procedure which might befollowed in implementing the IAEA/NEA(OECD)/ILO/WHO BasicSafety Standards for Radiation Protection.


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Contents: 1. Introduction; 2. Basic concepts; 3. Definitions of prac-tice and source; 4. Principles for exemption; 5. Application of theprinciples for exemption to a single practice; 6. Preparation andadministration of exemptions; Annex: Examples of definitions ofsome practices and sources.


PROVISION OF OPERATIONAL RADIATION PROTECTIONSERVICES AT NUCLEAR POWER PLANTS Safety Series No. 103

This publication gives guidance on the radiation protection servicesthat are needed during the operation of a nuclear power plant toachieve acceptable performance in radiation safety and on the opti-mization process that must be applied to these sevices to complywith the ALARA principle. It presents a broad overview of environ-mental monitoring, radioactive waste management, emergency plan-ning, the transportation of radioactive material and the analyticalservices associated with the assessment of internal and external radi-ation doses.

Contents: 1. Introduction; 2. A review of the system of dose limita-tion for radiation protection; 3. Development of a general opera-tional radiation protection programme; 4. Organization and manage-ment; 5. Personnel selection and training; 6. Occupational radiationcontrol; 7. Public radiation control; 8. Review of major factorsaffecting the optimization of operational radiation protection in anuclear power plant; Annex I: Practical seven stage framework forthe optimization of a complete operational programme; Annex II:Example of a policy statement for radiation protection.


RADIATION AND SOCIETY: ➜NEWCOMPREHENDING RADIATION RISKProceedings Series

Proceedings of an international conference, Paris, 24–28 October1994. Upon a request by the IAEA, the Swedish Risk Academycommissioned a set of background papers on issues relating to thecomprehension of radiation risk to serve as a scientific input for theconference. The papers cover topics of importance for risk assess-ment and for comprehending and communicating on radiation risk.

Contents: (Vol. 1) 1. Introduction; 2. Comprehending radiation risk;3. The concept of probability; 4. Risk perception; 5. Interpretingepidemiological results; 6. Problems in radiation risk assessment; 7.Cause structure of global mortality; 8. Radiation levels; 9. Problemsin risk comparisons; 10. Risk communication; 11. Risk and ethics.(Vol. 2) Background papers prepared for the conference by IPSN;Poster presentations: Assessment of radiation exposure levels;Assessment of radiation health effects; Impact of radiation on theenvironment; Perception of radiation risk; Managing radiation risk;The nuclear weapons legacy; Cancer and leukaemia clusters; Radonin homes; Radioactive waste disposal and the environment; Cher-nobyl health effects. (Vol. 3) Conference summary; Openingaddresses; Technical sessions; Case study sessions; Special lecture,closing adresses; Media forums, media and policy makers forum,decision makers session.

STI/PUB/959 (Vol. 1: 196 pp., 7 figures; 1994; Vol. 2: 455 pp.,84 figures; 1996; Vol. 3: 249 pp., 13 figures; 1997)

1: ISBN 92–0–102194–12: ISBN 92–0–103096–73: ISBN 92–0–101197–0Price: Vol. 1: 640 Austrian schillings (€46.51)

Vol. 2: 1360 Austrian schillings (€98.84)Vol. 3: 760 Austrian schillings (€55.23)

RADIATION MONITORING IN THE MINING AND MILLING OF RADIOACTIVE ORES Safety Series No. 95

(See under Uranium Mining and Milling, p. 26)

RADIATION PROTECTION AND THE ➜NEWSAFETY OF RADIATION SOURCES: A Safety FundamentalSafety Series No. 120

(See under Radiation Sources and Accelerators, p. 52)

RADIATION PROTECTION DURING OPERATION OF NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-O5


RADIATION PROTECTION IN NUCLEAR ENERGY Proceedings Series

Proceedings of a conference, Sydney, Australia, 18–22 April 1988.The purpose of the conference was to exchange views on theprinciples of radiation protection, to highlight issues of currentimportance, to examine the problems encountered in applying theprinciples of radiation protection and, where possible, to identifygeneric solutions. The important topics covered were the interfacebetween nuclear safety and radiation protection, practices exemptedfrom regulatory control, a review of the dosimetry of the Hiroshimaand Nagasaki survivors, derived intervention levels and theexperience gained from the Chernobyl and Goiânia accidents. Anadditional feature of the conference was the inclusion of two keydiscussion sessions on the linear dose–response relationship and oneducation and training in radiation protection.

Contents: (Vol. 1) Opening session; Nuclear safety and radiationprotection; Evolution of radiation protection principles; Regulationof radiation protection; Optimization and decision aiding; Thedose–response relationship: Implications for nuclear energy; Panel1. The dose–response relationship in practice: Problems and solu-tions; (Vol. 2) Occupational radiation protection; Limitation ofradioactive releases; Safe disposal of radioactive wastes; Radio-logical impact of nuclear facilities; Accident response planning;Accident experiences; Panel 2. Radiation protection education andtraining; Summary of the Conference and closing remarks.

STI/PUB/783 (Vol. 1: 494 pp., 72 figures; Vol. 2: 522 pp., 68 figures; 1988)1: ISBN 92–0–020388–4 2: ISBN 92–0–020488–0 Price: Vol. 1: 1200 Austrian schillings (€87.21)


RADIATION PROTECTION INFRASTRUCTURE Proceedings Series

Proceedings of a symposium, Munich, 7–11 May 1990. The expand-ing application of ionizing radiation in medicine, industry andresearch calls for vigorous promotion of effective radiation protec-tion efforts, not only to prevent any unsafe practices but also to


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assess correctly and provide authoritative information on the safetyof adopted practices. The purpose of the symposium was to reviewexperience gained in Member States with existing infrastructures forensuring radiation safety and to discuss how safety standards couldmost effectively be applied in the national context.

Contents: Regulation and licensing; National infrastructures;Education and training; Personnel dosimetry services; Controlprogrammes; Services and special issues; International activities;Panel: The role of the IAEA in strengthening radiation protectioninfrastructures.


R A D I O L O G I C A L A S S E S S M E N T R E P O R T S S E R I E S

This series comprises reports on assessments made by the IAEA inareas around the world that are contaminated by radioactive residuesfrom past activities conducted without applying international radia-tion protection standards. Such residues result from peaceful activi-ties such as uranium mining and milling as well as from militaryactivities that were outside the scope of international standards,including the production and testing of nuclear weapons.

RADIOLOGICAL CONDITIONS AT BIKINI ATOLL: ➜NEWPROSPECTS FOR RESETTLEMENTRadiological Assessment Reports Series

The general concern about the state of the environment has focusedthe attention of many countries in recent years on the need to reme-diate areas affected by radioactive residues. The present assessmentwas requested by the Government of the Republic of the MarshallIslands, with the purpose of obtaining an independent view of theradiological situation on Bikini Atoll, the site of nuclear weaponstesting in the period 1946–1958. In particular, questions were posedabout whether the former inhabitants should be permitted to returnto their homes and about the nature and extent of any remedialactions which might be necessary. This report presents the resultsand conclusions of a meeting of international experts convened bythe IAEA and chaired by K. Lokan, Australia, in December 1995 toreview the available information on the subject.

Contents: 1. Summary; 2. The Marshall Islands; 3. Background:Nuclear weapon testing in the Marshall Islands and its aftermath atBikini Atoll; 4. The international review; 5. Radiological concepts inthe context of nuclear weapon testing; 6. Present environmentalradiological conditions at Bikini Atoll; 7. Estimates of potentialradiation doses to people resettling Bikini island under presentconditions; 8. Radiation protection criteria; 9. Habitability of Bikiniislands; 10. Conclusions and recommendations; References; Adden-dum: IAEA corroboratory monitoring mission to Bikini island.


RADIOLOGICAL CONDITIONS AT THE ➜NEWSEMIPALATINSK TEST SITE, KAZAKHSTAN: Preliminary Assessment and Recommendations for Further StudiesRadiological Assessment Reports Series

This report presents the findings of a study of the current radio-logical conditions at the former nuclear test site at Semipalatinsk,Kazakhstan, conducted by a team of international experts under theauspices of the IAEA at the request of the Government of Kazakh-

stan. The objectives of the study were to assess the current andpotential future radiation doses to the residents of the Semipalatinsknuclear test site area and adjacent settlements, to advise on remedialaction, where appropriate, and to recommend whether further radio-logical evaluation of the area is warranted.

Contents: 1. Summary; 2. The Semipalatinsk test site; 3. Back-ground; 4. Programme of IAEA assistance; 5. Perspective on globalnuclear weapons testing; 6. Radiological conditions at the Semi-palatinsk test site; 7. Estimates of present and future doses topersons in and around the test site; 8. Radiation protection criteria;9. Conclusions and recommendations; Appendix: Method of assess-ing radiation doses.


RADIOLOGICAL CONDITIONS OF ➜NEWTHE WESTERN KARA SEARadiological Assessment Reports Series

This report presents the findings of the International Arctic SeasAssessment Project (IASAP), which was designed to addressconcerns over the potential health and environmental impacts ofhigh level radioactive waste dumped in the shallow waters of theArctic Seas. The following aspects were covered: (i) examination ofthe current radiological situation in Arctic waters due to the dumpedwastes; (ii) evaluation of potential future releases from the dumpedwastes; (iii) prediction of environmental transport of potentialreleases and assessment of the associated radiological impact onhumans and biota; and (iv) examination of the feasibility, costs andbenefits of possible remedial measures.

Contents: Executive summary; 1. Introduction; 2. Radiologicalprotection and decision making; 3. The Arctic environment; 4. Theradioactive source term; 5. Environmental modelling for radiologi-cal impact assessment; 6. Possible remedial actions; 7. Analysis ofthe need for remedial actions; 8. Conclusions and recommendations.


THE RADIOLOGICAL SITUATION AT THE ATOLLS OF MURUROA AND FANGATAUFA Reports by an International Advisory CommitteeRadiological Assessment Reports Series

The Study of the Radiological Situation at the Atolls of Mururoa andFangataufa was conducted at the request of the Government ofFrance to determine whether, as a consequence of French nucleartests conducted above and beneath these atolls, radiological hazardscould arise, now or in the future; and to recommend the form, scaleand duration of any monitoring, remedial action or follow-up actionthat might be required. An International Advisory Committee wasconvened by the Director General of the IAEA to provide scientificdirection and guidance on the conduct of the Study. The firstmeeting of the IAC was held in April 1996 and its final meeting inFebruary 1998. In addition to IAEA Secretariat staff, 55 scientistsfrom 18 countries and four international organizations participatedin the Study, including the environmental sampling and surveillancecampaigns, which involved 18 laboratories in 12 countries.

The results of the Study are presented in four separate publications:The Main Report; the Executive Summary (which is also incorpo-rated in the Main Report); the Summary Report; and the TechnicalReport. The Main Report is the primary publication of the Study andprovides a comprehensive scientific account, together with findings,


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conclusions and recommendation. The Executive Summary is repro-duced from the original document presented to the IAEA Board ofGovernors. The Summary Report provides an extended synopsis ofthe Study for the benefit of a wider audience, and includes its find-ings, conclusions and recommendation in full. The Main Report issupported by the detailed Technical Report in six volumes, which isintended for the scientific specialist.

An international Conference was held from 29 June to 3 July 1998to present the Study to the scientific community. The proceedingscan be obtained with the Technical Report.

The Executive Summary and the Summary Report are availableseparately as priced publications. Purchasers of the Main Report(which incorporates the Executive Summary) will also receive theSummary Report at no extra cost, and may obtain the TechnicalReport in six volumes and the Conference proceedings at no extracharge by returning the reply card included with the Main Report.

THE RADIOLOGICAL SITUATION ➜NEWAT THE ATOLLS OF MURUROA AND FANGATAUFA: Executive SummaryReport by an International Advisory CommitteeRadiological Assessment Reports Series

SITUATION RADIOLOGIQUE SUR LES ATOLLS DE MURUROA ET DE FANGATAUFA: SynthèseRapport par un Comité consultatif internationalCollection Rapports d’évaluations radiologiques

The Executive Summary, which is incorporated in the Main Reportand also available separately, presents a synopsis of the Main Reportfor the benefit of persons with executive, managerial or administra-tive responsibilities, together with its findings, conclusions andrecommendation. It is issued as one single publication in Englishand French.

Contents/Table des matières: Introduction/Introduction; Objec-tive/Objectif; Framework/Cadre; Conduct of the Study/ Conduite del’étude; Reports resulting from the Study/Rapports résultant del’étude; Findings/Résultats; Conclusions/Conclusions; Recommen-dation/Recommandation; Participants in the Study/Personnes ayantparticipé à l’étude.

STI/PUB/1028/ES (26 pp., 21 × 30 cm; 1998)ISBN 92–0–001898–XPrice: 200 Austrian schillings (€14.53)

THE RADIOLOGICAL SITUATION ➜NEWAT THE ATOLLS OF MURUROA AND FANGATAUFA: Main ReportReport by an International Advisory CommitteeRadiological Assessment Reports Series

The Main Report, which incorporates the bilingual (English/French) Executive Summary (see above), gives a comprehensivescientific account of the Study, together with data on the Frenchnuclear weapon tests. It presents the results of the Study’s assess-ment of the environmental legacy of weapon testing at the atolls andestimates of consequent radiation doses at present and in the future,drawing on the supporting detailed Technical Report. The findings,conclusions and recommendation are presented, together with anaccount of their basis in radiation protection and further backgroundmaterial to provide perspective.

Contents: Executive Summary; Part A: Background: 1. The Study;2. Geography, geology and history of the atolls; 3. Nuclear testingprogramme; Part B: Present and predicted radiological situations:4. Inventory of residual radioactive material in the biosphere at the

atolls; 5. Inventory of residual radioactive material in the geosphereof the atolls; 6. Transport of residual radioactive material throughthe geosphere; 7. Effects of hypothetical disruptive events; 8. Trans-port of residual radioactive material through the marine environ-ment; Part C: Results I; 9. Radiation doses and their potential forimpact on human health; 10. Potential impact of radiation doses onbiota; 11. The need for remediation; Perspective; Part D: Conclu-sions and recommendations; 12. Findings; 13. Conclusions;14. Recommendation; References; Annex I: Retrospective assess-ment of the radiation doses attributable to atmospheric testing at theatolls; Annex II: Ciguatera: Incidence and cause; Annex III: Ioniz-ing radiation: Levels and biological effects; Annex IV: Some fissionand fusion physics and the testing of nuclear weapons; Glossary.

Purchasers of the Main Report will automatically receive theSummary Report at no extra cost.

STI/PUB/1028 (282 pp., 132 figures, 21 × 30 cm; 1998)E ISBN 92–0–101198–9F ISBN 92–0–203498–2Price: 1200 Austrian schillings (€87.21)

THE RADIOLOGICAL SITUATION ➜NEWAT THE ATOLLS OF MURUROA AND FANGATAUFA: Summary ReportReport by an International Advisory CommitteeRadiological Assessment Reports Series

The Summary Report provides a synopsis of the Study for thebenefit of a wider audience, and includes its findings, conclusionsand recommendation in full. It explains the background to the Study,giving data on the French nuclear weapon tests, and summarizes theStudy’s assessment of the environmental legacy of weapon testing atthe two atolls. The Study’s estimates of consequent radiation dosesat present and in the future are summarized. The basis in radiationprotection for the Study’s conclusions and recommendation ispresented in brief. Additional material to aid understanding andprovide perspective is included in 14 text boxes.

Contents: Introduction; The nuclear weapon tests conducted byFrance in the South Pacific; The Study and the International Advi-sory Committee; Assessment of present radiological conditions;Assessment of future radiological conditions; Estimated doses dueto residual radioactive material; Conclusions and recommendation;Annex: French nuclear tests at the atolls of Mururoa and Fangataufa.



Electron linear accelerators are being used throughout the world inincreasing numbers in a variety of important applications. Foremostamong these is their role in the treatment of cancer. Commercialuses include non-destructive testing by radiography, food preserva-tion, product sterilization and radiation processing of materials suchas plastics and adhesives. Scientific applications include investiga-tions in radiation biology, radiation chemistry, nuclear and elemen-tary particle physics and radiation research. This manual providesauthoritative guidance in radiation protection for this important cate-gory of radiation sources.

Contents: Introduction; Uses and characteristics of electron linearaccelerators; Radiation at electron linear accelerator installations;


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Radiation shielding; Typical installations; Radiation monitoring andinterpretation of measurements; Requirements for an effectivesafety programme; General bibliography; Appendices.



This report serves as a guide for the planning and implementation ofradiation protection programmes for all types of positive ion accel-erators. The basic types of accelerators are briefly described,followed by a detailed description of several installations coveringthe energy range from 10 MeV to 500 GeV. Special emphasis isgiven to the production of ionizing radiation and its transmissionthrough shielding, computer techniques for shield design, radiationmeasurement and interpretation, and the radiological impact ofaccelerators on the environment. Extensive references are given sothe book can serve as a source to the published literature.

Contents: Introduction; Characteristics of positive ion accelerators;Radiation environment of positive ion accelerators; Radiationmeasurements at accelerators; Radiation shielding; Accelerator radi-ation safety programme; Radiological environmental impact ofaccelerators; Sources of information and bibliography on accelera-tor radiation protection.


SAFE HANDLING OF TRITIUMTechnical Reports Series No. 324

This publication contains information on the dosimetry andmonitoring of tritium, the use of protective clothing for work withtritium, safe practices in tritium handling laboratories and details oftritium compatible materials. The information has been compiledfrom experience in the various applications of tritium and shouldrepresent valuable source material to all users of tritium, includingthose involved in fusion R&D.

Contents: 1. Introduction; 2. Radiological hazards and dosimetry;3. Tritium monitoring; 4. Personal protective clothing; 5. Propertiesand compatibility of materials for safe practice in tritium containingsystems; 6. Management of tritiated wastes; 7. Safe handling oftritium in laboratories; Annex I: Gaseous tritium light source manu-facturing; Annex II: Commercial radiochemical manufacturing;Annex III: Safe handling of tritium in low and medium level univer-sity and medical facilities; Annex IV: Tritium safe handling in heavywater reactors.



The IAEA Safety Standards Series comprises publications of a regu-latory nature covering nuclear safety, radiation protection, radioac-tive waste management, the transport of radioactive materials, thesafety of nuclear fuel cycle facilities and quality assurance. Thesepublications are issued under the terms of Article III of the Agency’sStatute, which authorizes the Agency to establish standards of safety

for protection against ionizing radiation. The Safety StandardsSeries supersedes the Safety Series, in which over 200 publicationswere issued. Safety Standards Series publications are categorizedinto:





RADIOLOGICAL SAFETY

For Safety Requirements see Safety Series No. 115, INTER-NATIONAL BASIC SAFETY STANDARDS FOR PROTECTION AGAINSTIONIZING RADIATION AND THE SAFETY OF RADIATION SOURCES,p. 59.

OCCUPATIONAL RADIATION ➜NEWPROTECTION: Safety GuideSafety Standards Series No. RS-G-1.1

The present Safety Guide provides general guidance on the estab-lishment of an effective radiation protection programme for occupa-tional exposure, appropriate for the sources of radiation likely to beencountered in a range of industries, medical institutions, educa-tional and research establishments and nuclear fuel cycle facilities.The report further provides the necessary guidance to meet therequirements as laid down in Safety Series No. 115, InternationalBasic Safety Standards for Protection against Ionizing Radiationand for the Safety of Radiation Sources (1996).

Contents: 1. Introduction; 2. Framework for occupational radiationprotection; 3. Dose limitation; 4. Optimization of radiation protec-tion for practices; 5. Radiation protection programmes; 6. Interven-tion in emergencies; 7. Health surveillance.

Arabic, Chinese, French, Russian and Spanish editions planned.


ASSESSMENT OF OCCUPATIONAL ➜NEWEXPOSURE DUE TO INTAKES OF RADIONUCLIDES: Safety GuideSafety Standards Series No. RS-G-1.2

The present Safety Guide addresses the assessment of exposure dueto intakes of radionuclides in the workplace and reflects the majorchanges which have occurred in international practice in internaldose assessment over the past decade. The report further providesthe necessary guidance to meet the requirements as laid down inSafety Series No. 115, International Basic Safety Standards forProtection against Ionizing Radiation and for the Safety of RadiationSources (1996).


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Contents: 1. Introduction; 2. Dosimetric quantities; 3. Monitoringprogrammes; 4. Direct methods; 5. Indirect methods; 6. Biokineticmodels for internal dosimetry; 7. Interpretation of measurements;8. Dose record keeping and reporting; 9. Quality assurance; Appen-dix I: Suggested criteria for individual monitoring; Appendix II:Detection limits for measurement methods; References; Annex I:Basic data.



ASSESSMENT OF OCCUPATIONAL EXPOSURE ➜NEWDUE TO EXTERNAL SOURCES OF RADIATION: Safety GuideSafety Standards Series No. RS-G-1.3

The present Safety Guide addresses the assessment of exposure toexternal sources of radiation in the workplace and the monitoring ofworkers and the workplace in such situations. It also reflects themajor changes over the past decade in international practice in exter-nal dose assessment. It further provides the necessary guidance tomeet the requirements as laid down in Safety Series No. 115, Inter-national Basic Safety Standards for Protection against IonizingRadiation and for the Safety of Radiation Sources (1996).

Contents: 1. Introduction; 2. Dosimetric quantities; 3. Monitoringprogrammes; 4. Dosimetric specifications; 5. Type testing; 6. Pre-use and periodic testing; 7. Performance testing; 8. Dose recordkeeping and reporting; 9. Quality assurance; Appendix: Monitoringfor skin contamination and assessment of skin dose; References;Annex I: Summary of recommended radiation weighting factors andQ–L relationships; Annex II: Instrumentation for individual moni-toring; Annex III: Instrumentation for workplace monitoring; AnnexIV: Reference conditions and standard test conditions; Annex V:Data relevant to type testing of personal dosimeters and area moni-tors in terms of the operational quantities; Annex VI: Examples ofIEC standards on radiation monitoring equipment.



THE APPLICATION OF THE PRINCIPLES FOR LIMITINGRELEASES OF RADIOACTIVE EFFLUENTS IN THE CASE OFTHE MINING AND MILLING OF RADIOACTIVE ORES Safety Series No. 90

This publication provides general guidance on the application ofSafety Series No. 77 (1986), Principles for Limiting Releases ofRadioactive Effluents into the Environment, to the setting of limitsfor the release of radioactive substances during normal operation ofthe mining and milling of radioactive ores, as well as general guid-ance on assessing the resulting individual and collective doses.

Contents: 1. Introduction; 2. Basic concepts; 3. Sources of radionu-clide releases from uranium mining and milling facilities;4. Methodology for calculating doses to individuals resulting fromreleases; 5. Optimization of release control; 6. Guidance for appli-cation; Appendix.


THE INTERNATIONAL CHERNOBYL PROJECTAssessment of Radiological Consequences and Evaluation of Protective Measures: Reports by an International Advisory Committee

The International Chernobyl Project was launched in 1990 at therequest of the Government of the USSR to assess the environmentaland health situation in the areas of the Soviet Union contaminated bythe Chernobyl accident and to evaluate the measures taken by theauthorities to safeguard the health of the population still living in theseareas. Some 200 scientists from 25 countries and 7 international andregional organizations participated in this Project. An InternationalAdvisory Committee was set up to oversee the Project and approve itsconclusions and recommendations. Almost 50 missions to the USSRwere carried out in order to obtain the best available information andto make an independent assessment of the situation.

The results of the International Chernobyl Project are presented intwo main documents: The full Technical Report, which contains, inaddition to the conclusions and recommendations of the Project, allthe relevant methodologies and the data upon which they are based,and the Overview, which gives a summary of the methodologiespresented in the Technical Report together with the conclusions andrecommendations. While the Technical Report is intended for thescientific community, the Overview is intended for decision makers,concerned groups and the informed public. Three maps showing thedistribution of surface ground contamination by plutonium, stron-tium and caesium released by the Chernobyl accident and depositedin the Byelorussian SSR, the Russian SFSR and the Ukraine areattached to the Overview. A third document, containing theproceedings of an International Conference which took place inVienna in May 1991, presents the Project results to the scientificcommunity and to the media. The Proceedings should be read inconjunction with either the Overview or the Technical Report.

THE INTERNATIONAL CHERNOBYL PROJECT:An Overview

Contents: Chapter 1: The International Chernobyl Project;Chapter 2: Environmental contamination; Chapter 3: Radiationexposure of the population; Chapter 4: Health impact; Chapter 5:Protective measures; Appendix: Historical portrayal; Epilogue;International Advisory Committee.

STI/PUB/884 (57 pp., 23 figures, 3 surface contamination maps, 21 × 24 cm;1991)E ISBN 92–0–129091–8R out of printPrice: 280 Austrian schillings (€20.35)

THE INTERNATIONAL CHERNOBYL PROJECT:Proceedings of an International Conference held in Vienna, 21–24 May 1991, for presentation and discussion of the Technical Report

Contents: Programme of the Conference; Director General’sopening address; Chairman’s opening address; Introductory addressby the Head of the USSR delegation; M. Rosen: The InternationalChernobyl Project; P. Waight: WHO’s International Programme onthe Health Effects of the Chernobyl Accident (IPHECA); Session 2:Environmental contamination; Session 3: Radiation exposure of thepopulation; Sessions 4 and 5: Health impact; Session 6: Protectivemeasures; Section 7: Management of contaminated agriculturalareas; Panel discussion: The lessons learned; The Director General’sclosing remarks; Chairman’s closing remarks.

STI/PUB/894 (93 pp., 21 × 29.7 cm; 1991)ISBN 92–0–129391–7Price: 280 Austrian schillings (€20.35)


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THE INTERNATIONAL CHERNOBYL PROJECT:Technical Report

Contents: Part A. Introduction; Part B. Broadening understanding;Part C. Historical portrayal; Part D. Environmental contamination;Part E. Radiation exposure of the population; Part F. Health impact;Part G. Protective measures; Part H. Conclusions and recommenda-tions; Annex I: 137Cs and 90Sr contamination levels; Annex II: Ques-tions put to experts.

STI/PUB/885 (640 pp., 238 figures, 21 × 29.7 cm; 1991)E ISBN 92–0–129191–4R ISBN 92–0–400192–5Price: 1800 Austrian schillings (€130.81)

THE RADIOLOGICAL ACCIDENT IN GOIÂNIA


THE RADIOLOGICAL ACCIDENT IN SAN SALVADOR




THE RADIOLOGICAL ACCIDENT IN TAMMIKU ➜NEW(see under Accident Response, p. 72)

THE RADIOLOGICAL ACCIDENT IN ➜NEWTHE REPROCESSING PLANT AT TOMSK

(see under Accident Response, p. 72)

Accident Response

ACCIDENT MANAGEMENT PROGRAMMES IN NUCLEAR POWER PLANTS: A GuidebookTechnical Reports Series No. 368

This guidebook provides a systematic, structured approach to thedevelopment and implementation of plant specific accident manage-ment programmes. It describes the major elements of accidentmanagement and their relationships, presents possible methods andtechniques to solve specific problems and gives practical examples.Its main emphasis is on generic accident management guidelines,including evaluation of vulnerabilities, accident management strate-gies, symptom oriented emergency operating procedures, systemutilization, training and organization.

Contents: 1. Introduction; 2. Basic principles of accident manage-ment; 3. Framework for the development and implementation of anaccident management programme; 4. Summary and conclusions;References; Annex I: Accident management directing principles;Annex II: Example of a guideline for the development of an accidentmanagement programme; Annex III: Example of application of thedevelopment of an accident management programme to a severeaccident; Annex IV: Assessment of vulnerabilities; Annex V: Acci-dent management procedures and guidance.


ACCIDENTAL OVEREXPOSURE ➜NEWOF RADIOTHERAPY PATIENTS IN SAN JOSE, COSTA RICA

This report summarizes the assessment made of an accidental over-exposure of radiotherapy patients that occurred at the San Juan deDios Hospital in San José, Costa Rica, in August and Septem-ber 1996. The assessment was carried out by an Expert Teamconvened by the IAEA in July 1997 at the request of the Govern-ment of Costa Rica. The findings of the Expert Team’s assessmentare presented in two parts: (1) an evaluation of the doses to patientsby analysing the treatment records and physical measurements; and(2) a medical examination of patients, together with the autopsyfindings for those who died. Thirty cross-sectional images are repro-duced that show the dose reconstructions made for some of thepatients. The purpose of the report is to foster information exchangewith a view to preventing similar accidents in the future.

Contents: Preface; Executive Summary; 1. Overview of radio-therapy and radiation protection; Part I. Background; 2. History ofthe accident; 3. Expert Assessment organized by the IAEA; Part II.Findings of the Expert Team; 4. Assessment of the dosimetry and thestatus of the equipment and the facility; 5. Medical effects of radia-tion exposure of the patients; Part III. Conclusions and recommen-dations; 6. Conclusions and recommendations; Appendix I: Resultsof the dosimetric findings and the status of the equipment and thefacility; Appendix II: Data on patients; Annex: Records on theparticipation of the San Juan de Dios Hospital in the IAEA/WHOTLD postal dose quality audit; Addendum: Reconstruction of thedoses to normal tissue for patients with marked adverse effects.

STI/PUB/1027 (176 pp., 45 figures; 1998)E ISBN 92–0–102098–8S ISBN 92–0–302799–8Price: 600 Austrian schillings (€43.60)

AN ELECTRON ACCELERATOR ACCIDENT ➜NEWIN HANOI, VIET NAM

On 17 November 1992 a radiological accident occurred at an elec-tron accelerator facility in Hanoi, Viet Nam. An individual enteredthe irradiation room without the operators’ knowledge and unwit-tingly exposed his hands to the X ray beam. His hands were seri-ously injured and one hand had to be amputated. The report detailsthe circumstances of the accident, its medical consequences and thegovernmental response.

Contents: 1. Introduction: 1.1. Background to the IAEA post-accident review; 2. Regulatory control in Viet Nam; 3. Theirradiation facility: 3.1. Facility origins and layout; 3.2. Acceleratordesign and operation; 3.3. Safety systems and procedures; 4. Theaccident and the response: 4.1. The accident; 4.2. The response;5. Medical management: 5.1. Before hospitalization; 5.2. In hospitalin Hanoi; 5.3. Specialized treatment in Paris; 6. Assessment of thedose to the patient: 6.1. Post-accident measurements at the facility;6.2. Materials exposed in the accident; 7. Lessons learned: 7.1.Conclusions; 7.2. Recommendations to organizations operating irra-diation facilities; 7.3. General recommendations to regulatoryauthorities; 7.4. Recommendation to medical authorities;7.5. Recommendations to equipment suppliers; Annex.

STI/PUB/1008 (36 pp., 15 figures; 1996)E ISBN 92–0–100496–6Price: 200 Austrian schillings (€14.53)

R A D I A T I O N P R O T E C T I O N — A C C I D E N T R E S P O N S E

68

CLEANUP OF LARGE AREAS CONTAMINATED AS A RESULT OF A NUCLEAR ACCIDENTTechnical Reports Series No. 300

Experience at Chernobyl showed that the main long term radiologi-cal consequence to the population will probably be external expo-sure from radioactive fallout deposited on the ground. The presenttext provides an overview of the methodology and technology avail-able for cleaning up large areas and gives preliminary guidance onthe planning, implementation and management of such cleanups.

Contents: 1. Introduction; 2. Purposes of the report; 3. Scope;4. Planning the cleanup; 5. Managing the cleanup; 6. Characterizingthe affected area; 7. Deposition of contamination on surfaces;8. Characterizing the contamination; 9. Stabilization of contamina-tion; 10. Decontamination techniques and equipment; 11. Interdic-tion of an area; 12. Application of cleanup technology to situationsinvolving high radiation fields; 13. Loading and transporting largevolumes of wastes; 14. Disposal of large volumes of wastes;15. Radiation protection and safety; 16. Conclusions and recom-mendations; Annex A: The cleanup after the accident at the Cher-nobyl nuclear power plant.


DERIVED INTERVENTION LEVELS FOR APPLICATION IN CONTROLLING RADIATION DOSES TO THE PUBLIC IN THE EVENT OF A NUCLEAR ACCIDENT OR RADIOLOGICALEMERGENCY: PRINCIPLES, PROCEDURES AND DATASafety Series No. 81


DIAGNOSIS AND TREATMENT ➜NEWOF RADIATION INJURIESSafety Reports Series No. 2

The main purpose of this report is to assist physicians involved inthe early medical handling of radiation victims to apply promptdiagnostic measures and emergency treatment. Special emphasis isgiven to localized radiation injuries, which are the most frequentlyoccurring direct health effects observed from ionizing radiation. Thelessons learned from the accidents at Chernobyl (Ukraine, 1986),Goiânia (Brazil, 1987), San Salvador (El Salvador, 1989), Soreq(Israel, 1990) and Nesvizh (Belarus, 1991) on the early medicalhandling of radiation injuries have been incorporated into thisreport.

Contents: 1. Introduction; 2. Types of accidental exposure and theirmedical management; 3. External exposure; 4. Contamination withradionuclides; 5. Combined radiation injuries; 6. Consulting system;7. Record keeping; References; Annex I: Accidental exposure formsamples; Annex II: Diagnosis and treatment of persons exposed tocaesium-137: The Goiâna experience


DISPOSAL OF WASTE FROM THE CLEANUP OF LARGE AREAS CONTAMINATED AS A RESULT OF A NUCLEAR ACCIDENTTechnical Reports Series No. 330

The problem of ground contamination in the case of a severe nuclearaccident is one of special concern. This report gives guidance onplanning and management of safe transportation and disposal of

large volumes of contaminated materials, with the objective of mini-mizing the consequences of such an accident. It is closely linked toTechnical Reports Series No. 300, Cleanup of Large Areas Contam-inated as a Result of a Nuclear Accident (1989), and No. 327, Plan-ning for Cleanup of Large Areas Contaminated as a Result of aNuclear Accident (1991).

Contents: 1. Introduction; 2. Purpose; 3. Scope; 4. Waste character-istics and quantities; 5. Treatment of wastes; 6. Scenarios for thetransportation and disposal of wastes; 7. Loading and transportationof large volumes of waste; 8. Disposal of large volumes of waste; 9.Disposal of facility operation, closure and surveillance; 10. Reviewof operational experience; 11. Radiation protection and safety plan;12. Conclusions; Appendix A: Radiological criteria required toimplement the cleanup of large areas after an accident at a nuclearfacility; Appendix B: A generic method for estimating costs of wasteloading, transportation and disposal; Appendix C: Experience inCanada with the transportation and long term management ofradioactively contaminated soils; Appendix D: Experience in theUSA with the transportation and disposal of radium contaminatedwaste; Appendix E: Transportation and disposal of large volumes ofcontaminated material arising from cleanup after the Chernobylaccident.


EMERGENCY PLANNING AND PREPAREDNESS FOR ACCIDENTS INVOLVING RADIOACTIVE MATERIALS USED IN MEDICINE, INDUSTRY, RESEARCH AND TEACHINGSafety Series No. 91

The widespread use of radiation sources in medicine, agriculture,industry, research and teaching, in spite of all the precautions taken,may cause accidents which result in injury or death of persons anddamage to property. All practical steps to prevent such accidentsmust be taken and emergency actions planned in advance in order tolimit injuries and damage. Emergency plans should be sufficientlybroad to cover unforeseen or very improbable accidents as well asthose that are considered more likely. Such plans should be estab-lished by the users of radioactive materials as well as by local emer-gency agencies and national competent authorities.

Contents: Introduction; Accident analysis and action levels; Protec-tive measures; Planning for an emergency response; Procedures forimplementation; Medical aspects; Public information; Training andexercises; Maintaining and updating the emergency plans; Appen-dix I: Examples of accidents involving radioactive materials; Appen-dix II: Sample radiography contingency plan; Appendix III:A mobile intervention unit.


EMERGENCY PLANNING AND ➜NEWPREPAREDNESS FOR RE-ENTRY OF A NUCLEAR POWERED SATELLITE: A Safety PracticeSafety Series No. 119

Although the probability of nuclear powered satellite re-entries issmall, the present guidebook was prepared to assist States in plan-ning for possible re-entry events and to provide internationalconsensus guidance for responding to such a situation. In particular,this document provides guidance for specific actions to be taken


69

from the time of the announcement of an impending re-entry eventthrough the locating, monitoring and recovery phases.

Contents: 1. Introduction; 2. Risks associated with re-entry of anNPS; 3. Emergency planning and preparedness; Annex I: Guidancefor local organizations response (local police, civil defence, fire-fighting); Annex II: Guidance for hospitals; Annex III: Guidance forlocal agriculture organizations; Annex IV: Guidance on approachingdebris; Annex V: Example criteria for protective actions with respectto direct exposure to widely dispersed radioactive particles fromreactor powered satellites; Annex VI: Example guidance on decisioncriteria for protective actions with respect to direct exposure towidely dispersed radioactive particles; Annex VII: Guidance onestablishment of screening centres following re-entry; Annex VIII:Guidance concerning food use folllowing re-entry; Annex IX: Guid-ance concerning water use following re-entry.


EMERGENCY RESPONSE PLANNING AND PREPAREDNESS FOR TRANSPORT ACCIDENTSINVOLVING RADIOACTIVE MATERIALSafety Series No. 87

(See under Transport of Radioactive Material, p. 54)

GUIDELINES FOR AGRICULTURAL COUNTERMEASURESFOLLOWING AN ACCIDENTAL RELEASE OF RADIONUCLIDESTechnical Reports Series No. 363

This report is a collation of information and experience gained fromthe Chernobyl accident in 1986 concerning the transfer of radionu-clides, especially 137Cs and 90Sr, through food chains to man and theways to effectively reduce them. Included are accounts of measurestaken in various countries following the Chernobyl accident, whichat the time caused significant radioactive contamination of the envi-ronment over widely separated areas, some relatively remote fromthe site.

Contents: Part I. Introduction; 1. Introduction; 2. General consid-erations; 3. Developing a strategy for agricultural countermeasures;Part II. Agricultural countermeasures: Scientific basis and practice;4. Introduction; 5. Preventive measures to be applied before andduring the arrival of radioactive fallout; 6. Countermeasures to beapplied in the first few weeks after deposition; 7. Countermeasuresto be applied in the medium and long term; 8. Losses of radionu-clides in food by processing and culinary preparation; Part III. Orga-nizing for response; 9. Introduction; 10. Emergency preparedness;11. Response; 12. Public information and information forfarmers; Part IV. Contamination in agriculture from past nuclearaccidents; 13. Introduction; 14. Nuclear accident requiring counter-measures only in the short term; 15. Nuclear accident requiringcountermeasures in both the short and long term; Glossary.


iNTERVENTION CRITERIA IN A NUCLEAR OR RADIATION EMERGENCYSafety Series No. 109


LESSONS LEARNED FROM ACCIDENTS IN ➜NEWINDUSTRIAL IRRADIATION FACILITIES

The purpose of this publication is to present the results of a reviewof accidents in industrial radiography which have either beenreported to regulatory authorities or to professional associations, orbeen published in scientific journals. Use of ionizing radiation inmedicine, industry and research for technical development contin-ues to increase throughout the world. Although this industry has agood safety record, there is a potential for accidents with seriousconsequences to human health because of the high dose ratesproduced by these sources. Five fatal accidents occurred between1975 and 1994. Such accidents have prompted the present review,carried out by a team of manufacturers, regulatory authorities andoperating organizations. Having closely looked at the circumstancesof each accident, the apparent deficiencies in design, safety andregulatory systems, and personnel performance, the team made anumber of recommendations. The findings of extensive researchpertaining to the lessons that can be learned from irradiation acci-dents are presented.

Contents: 1. Introduction; 2. Brief description of accidents;3. Major causes of accidents and lessons learned; 4. Prevention andremedial actions; Annex: Accidents with fatal consequences andwith severe radiation injuries; References.

STI/PUB/1015 (52 pp., 10 figures; 1996)E ISBN 92–0–102696–XR ISBN 92–0–403597–8S ISBN 92–0–303497–8Price: 240 Austrian schillings (€17.44)

LESSONS LEARNED FROM ACCIDENTS IN ➜NEWINDUSTRIAL RADIOGRAPHYSafety Reports Series No. 7

This Safety Report contains the findings of extensive research interms of the lessons that can be learned from accidents which haveoccurred in industrial radiography, both in developed and develop-ing countries. The review was carried out by a team of regulatoryauthorities, manufacturers and safety advisers. The objectives wereto draw lessons from the initiating events of the accidents, thecontributing factors and the consequences, and to identify severalmeasures that, if implemented, would improve safety performancein industrial radiography.

Contents: 1. Introduction; 2. Primary causes of reported accidents;3. Lessons learned; 4. Prevention and remedial actions; Annex I:Radiation protection training programme for radiographers;Annex II: Considerations for the safety operating procedures; AnnexIII: Emergency plan; References; Glossary.


MEDICAL HANDLING OF ACCIDENTALLY EXPOSED INDIVIDUALSSafety Series No. 88


ON-SITE HABITABILITY IN THE EVENT OF AN ACCIDENT AT A NUCLEAR FACILITYSafety Series No. 98

In this report the term ‘habitability’ is used to describe a conditionthat determines whether or not occupancy by operating or

A C C I D E N T R E S P O N S E

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emergency response personnel of a ‘vital’ area of a nuclear installa-tion during an accident is possible on a continuous or transient basis.Improvements and corrective measures in habitability can bedesigned into new installations or implemented at existing facilities.The report provides guidance assessing habitability in existinginstallations and at the design stage for new plants and suggestsactions to improve habitability in the event of an accident.

Contents: 1. Introduction; 2. Key elements of a habitability assess-ment methodology; 3. A generic methodology for habitabilityassessment; 4. Improvement of habitability; 5. Assessment andimprovement of habitability after an accident has occurred; Appen-dix A: Example of assessing and improving habitability for a radio-logical type of accident scenario; Appendix B: Example of assessingand improving habitability for a non-radiological type of accidentscenario.

STI/PUB/812 (74 pp., 4 (3 colour) figures; 1989)ISBN 92–0–123889–4Price: 260 Austrian schillings (€18.89)

ONE DECADE AFTER CHERNOBYL — ➜NEWSumming Up the Consequences of the AccidentProceedings Series

Proceedings of an international conference, jointly sponsored bythe European Commission, IAEA and WHO, and held in co-operation with UNDHA, UNESCO, UNEP, UNSCEAR, FAO andOECD/NEA, Vienna, 8–12 April 1996. Two major objectives wereto reach agreement on established scientific facts and to clarifytheir interpretation in order to promote comprehension of theconsequences of the Chernobyl accident and to help dispel misap-prehensions. Background papers were prepared by teams of scien-tists from around the world who collaborated to ascertain andpresent the current state of knowledge on the health and environ-mental consequences of the accident. Nuclear safety aspects andthe accident’s social and economic impact were also considered, aswell as the conclusions drawn at related conferences and in othernational and international projects. The conference was attended bymore than 800 experts in the field of radiation protection andnuclear safety, including medical, environmental and engineeringspecialists. The conference did much to achieve a broad consensuson the accident’s consequences and to consolidate a commonunderstanding of their nature and magnitude. In particular, theresults of the conference will assist those countries most affected bythe consequences in developing well informed and balanced poli-cies for their alleviation. The proceedings contain a summary of theconference results and the texts of oral presentations and discus-sions, while an IAEA technical document (TECDOC) will repro-duce material from 181 poster presentations as well as the List ofParticipants.

Contents: Summary of the conference results; Opening session;Briefing seminar: Updating sessions; Keynote presentations. Tech-nical symposium: Topical session 1: Clinically observed effects;Topical session 2: Thyroid effects; Topical session 3: Long termhealth effects; Topical session 4: Other health related effects:Psychological consequences, stress, anxiety; Topical session5: Consequences for the environment; Topical session 6: Social,economic, institutional and political impact; Topical session7: Nuclear safety remedial measures; Topical session 8: The conse-quences in perspective: Prognosis for the future; Concluding sessionof the technical symposium; Panel discussion; Closing session.


PLANNING FOR CLEANUP OF LARGE AREAS CONTAMINATED AS A RESULT OF A NUCLEAR ACCIDENTTechnical Reports Series No. 327

The present report is the second of three IAEA publications dealingwith the cleanup of large areas contaminated as a result of a nuclearaccident. It is mainly a planning and management document, outlin-ing the broad strategic and tactical approach to cleanup, the manage-ment structure and other key requirements. The report also showshow the various subplans interface and interact to ensure thatcleanup can be performed safely, efficiently and as quickly as possi-ble under adverse conditions.

Contents: 1. Introduction; 2. Purpose; 3. Scope; 4. Responsibilitiesfor emergency planning and management; 5. Planning and manag-ing the cleanup; 6. Data management; 7. Geographical co-ordinategrid system; 8. Radiological survey plan; 9. Compliance withrelease criteria; 10. Logistic support; 11. Quality assurance plan; 12.Training and exercises; 13. Updating the preliminary cleanup plan.14. Radiation protection and safety of workers; 15. Summary;Appendix A: Brief review of cleanup methodology and technology;Appendix B: Examples of data management systems which could beapplied to the cleanup of large areas.


PLANNING THE MEDICAL RESPONSE ➜NEWTO RADIOLOGICAL ACCIDENTSSafety Reports Series No. 4

This Safety Report was jointly sponsored by the IAEA and WHO. Itoutlines the roles and tasks of health authorities and hospital admin-istrators in emergency preparedness for radiological accidents andprovides information relevant to the integration of medical prepared-ness into emergency plans.

Contents: 1. Introduction; 2. Classification of possible radiologicalaccidents; 3. Basic medical response to radiological accidents;Annex I: Major radiation accidents (1945–1997) in nuclear industry,non-nuclear industry, research and medicine involving workers aswell as members of the public; Annex II: List of internationalconsulting centres; Annex III: Plan of an ideal reception centre forradiation casualties.

STI/PUB/1055 (31 pp.; 1998)ISBN 92–0–102598–XPrice: 200 Austrian schillings (€14.53)

PREPAREDNESS OF PUBLIC AUTHORITIES FOR EMERGENCIES AT NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-G6

(See under Nuclear Power Plants, p. 33)

PREPAREDNESS OF THE OPERATING ORGANIZATION(LICENSEE) FOR EMERGENCIES AT NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-O6



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RECOVERY OPERATIONS IN THE EVENT OF A NUCLEAR ACCIDENT OR RADIOLOGICAL EMERGENCYProceedings Series

Proceedings of a symposium, Vienna, 6–10 November 1989. Thepurpose was to provide a forum for review of actual experiencegained and lessons learned from recovery techniques and operationsin response to serious accidents at nuclear facilities and accidentsassociated with radioactive materials, and also to consider the devel-opment of emergency planning and preparedness resources. Aspecial feature of the symposium programme was a full session onan accident involving a chemical explosion in a high level wastetank at a plutonium extraction plant in the Southern Urals in theUSSR in 1957.

Contents: Recovery operations from accidents with radioactivematerials; On-site recovery operations (nuclear facilities); Offsiterecovery operations (nuclear facilities); The accident in the SouthernUrals in 1957; Lessons learned from radiological accidents.

STI/PUB/826 (657 pp., 123 figures; 1990)ISBN 92–0–020290–XPrice 1750 Austrian schillings (€127.18)

THE RADIOLOGICAL ACCIDENT AT THE ➜NEWIRRADIATION FACILITY IN NESVIZH

On 26 October 1991, a fatal radiological accident occurred at anindustrial sterilization facility in Nesvizh, Belarus. Following a jamin the internal product transport system, the operator entered theirradiation chamber to clear the fault. In doing so, he bypassed anumber of safety features, leaving the controls in a position such thatexposure was imminent. It was estimated that he received a wholebody dose of 11 Gy, with localized areas of up to 20 Gy. Despiteintensive medical treatment, he died 113 days later. The significantfeature of this case was related to the medical management. In itspost-accident review, the IAEA also brought to light other circum-stances of the accident. The present report documents the causes andconsequences of the accident and defines the lessons learned with aview to assisting those people with responsibility for the safety ofsuch facilities and those medical authorities who might be involvedin the management of a radiation event.

Contents: 1. Introduction; 2. Irradiation facility; 3. Radiationaccident; 4. Dose estimation; 5. Lessons learned; 6. Medicalmanagement; Annex I: Estimation of whole body dose from bloodcell counts; Annex II: Results of cytogenetic analyses; Annex III:List of drugs, doses and administration dates.


THE RADIOLOGICAL ACCIDENTIN GOIÂNIA

The Government and authorities in Brazil were faced with a tragicaccident in Goiânia resulting from the misuse of a strongly radio-active medical teletherapy source not under radiation protectionsurveillance. The present report is divided into four parts: a chronol-ogy of destruction of the source, discovery of the accident and initialresponse; a description of the human consequences and the dosime-try and treatment of seriously exposed and contaminated persons; anaccount of the assessment of the environmental contamination andthe remedial actions taken; and observations and recommendations.Appendices and annexes give an assessment of the effectiveness ofinternational co-operation in the emergency response, and providefurther information on: public communications; radiological surveyequipment; guidelines for the discharge of patients; radiologicalprotection; chemical decontamination; and the lessons learned.

Contents: Executive summary; Part I. The accident: 1. Introduction;2. Background information; 3. Description of the accident; 4. Initialactions upon discovery of the accident; Part II. The human conse-quences: Dealing with the people affected; 5. Medical response; 6.Dosimetry; Part III. The environmental contamination: Assessmentand remedial actions; 7. Introduction and account of actions taken;8. Environmental assessments; 9. Decontamination; 10. Wastedisposal; Part IV. Observations and recommendations; Appendicesand annexes.

STI/PUB/815 (132 pp., 25 figures + 32 colour photographs; 1988)E ISBN 92–0–129088–8F ISBN 92–0–229089–XR ISBN 92–0–429089–7S ISBN 92–0–329089–3Price: 430 Austrian schillings (€31.25)

THE RADIOLOGICAL ACCIDENT IN SAN SALVADOR

On 5 February 1989, a radiological accident occurred at an indus-trial irradiation facility near San Salvador, El Salvador. Medicalproducts are sterilized at the facility by irradiation by means of anintensely radioactive cobalt-60 source in a movable source rack.This source rack became stuck in the irradiation position. The oper-ator bypassed the irradiator’s degraded safety systems and enteredthe radiation room with two other workers to free the source rackmanually. The three men were exposed to high radiation doses anddeveloped the acute radiation syndrome. They received initial hospi-tal treatment in San Salvador and subsequent, more specializedtreatment in Mexico City. The legs and feet of two men were so seri-ously injured that amputation was required. The worker who hadbeen most exposed died six and a half months after the accidentfrom lung damage due to irradiation complicated by injury sustainedduring treatment. The report describes the accident and the responseto it and presents lessons derived for operators and suppliers of irra-diators, national authorities, medical staff and international organi-zations. Detailed information on dosimetric and medical aspects ofthe accident is presented in appendices and annexes.

Contents: 1. Introduction; 2. The background in El Salvador; 3. Theirradiation facility; 4. The accident; 5. The response to the accident;6. Factors contributory to the accident; 7. Generic lessons learned;Addendum; Photographs; Appendix I: Dosimetric analysis; Appen-dix II: Medical treatment; Annexes I and II: Patients A and B: Nutri-tional reports by the Angeles del Pedregal hospital in Mexico City.

STI/PUB/847 (94 pp., 24 colour photographs, 20 figures; 1990)E ISBN 92–0–129090–XF ISBN 92–0–229090–3R ISBN 92–0–400292–1S ISBN 92–0–329091–5Price: 340 Austrian schillings (€24.71)


On 21 June 1990 a fatal radiological accident occurred at an indus-trial irradiation facility at Soreq, Israel. An operator entered the irra-diation room by circumventing safety systems and was acutelyexposed, with an estimated whole body dose of 10–20 Gy. The acci-dent, like earlier accidents at similar irradiators, was the conse-quence of the contravention of operating procedures. An IAEAreview team investigated the causes of the accident. This reportpresents its findings and recommendations and describes the clinicalmanagement of the patient, particularly of the haematological phase.The medical treatment included the use of emerging therapies withhaematopoietic growth factor drugs which may rescue the overex-posed patient, albeit in this case only temporarily. The report isintended for regulatory authorities responsible for the regulation andinspection of irradiators, operating organizations and physicianswho may need to treat overexposed patients.

A C C I D E N T R E S P O N S E

72

Contents: 1. Introduction; 2. The irradiation facility; 3. Regulatorycontrol; 4. The accident; 5. Actions and lessons; 6. Overview of themedical aspects; 7. Medical management of the patient; 8. Findingsof the post-mortem investigation; 9. Lessons to be learned.

STI/PUB/925 (78 pp., 14 figures + 32 illustrations; 1993)ISBN 92–0–101693–XPrice: 300 Austrian schillings (€21.80)

THE RADIOLOGICAL ACCIDENT ➜NEWIN TAMMIKU

In October 1994 three members of the public entered the radioactivewaste repository at Tammiku, Estonia, without authorization andremoved a metal container enclosing a radiation source, which oneof them placed in his pocket. This action resulted in the death of oneperson and injury to a number of others. The purpose of this reportis to provide information to help to ensure that similar accidents canbe avoided in the future.

Contents: 1. Introduction; 2. Radiation protection infrastructure inEstonia; 3. The accident; 4. Recovery of the source; 5. Subsequentactions; 6. Dosimetry; 7. Medical aspects; 8. Generic lessonslearned; Annex I: Physical dosimetry; Annex II: Biological dosime-try; Annex III: Medical findings..

Russian and Spanish editions in preparation.

STI/PUB/1053 (59 pp., 7 figures; 1998)E ISBN 92–0–100698–5Price: 280 Austrian schillings (€20.35)

THE RADIOLOGICAL ACCIDENT IN ➜NEWTHE REPROCESSING PLANT AT TOMSK

On 6 April 1993 a major radiological accident occurred at a pluto-nium extraction facility at a location then known as Tomsk-7,Russian Federation. The accident blew the concrete cover off thereaction vessel and led to widespread contamination of the site andthe surrounding area up to a distance of 28 km. The report describesthe events leading up to the accident and the radiological conse-quences. It provides a detailed description of the decontaminationand recovery operations and gives an analysis of their effectiveness.

Contents: Preamble; 1. Introduction; 2. Background information;3. Fuel reprocessing at the radiochemical works; 4. The accident andits cause; 5. Radiological situation after the accident; 6. SCE site;7. Surrounding area; 8. Recommendations.

Russian and Spanish editions in preparation.

STI/PUB/1060 (77 pp., 33 figures; 1998)E ISBN 92–0–103798–8Price: 320 Austrian Schillings (€23.26)

Radioactive Waste Management

AN OCEANOGRAPHIC MODEL FOR THE DISPERSION OF WASTES DISPOSED OF IN THE DEEP SEATechnical Reports Series No. 263

This document was originally approved by GESAMP (theIMO/FAO/UNESCO/WMO/WHO/IAEA/UN/UNEP Joint Group ofExperts on the Scientific Aspects of Marine Pollution) in March1983 at its thirteenth session for publication as GESAMP Reportsand Studies No. 19. Recognizing that its usefulness is far broaderthan its application to calculations of concentrations of radioactive

materials in the deep sea, the IAEA has undertaken to republish thereport in its Technical Reports Series with the concurrence of theother technical bodies of GESAMP.

Contents: Introduction; General requirements for ocean models forcontaminant transport; Oceanographic processes relevant to deep-sea contaminant transport; Survey of existing and potential models;Recommended models; Future research needs; Appendix I:Geochemical properties and observations of the deep ocean; Appen-dix II: Natural history of the ocean; Appendix III: Quantitative esti-mates of various biological processes; Appendix IV: A simple finiteocean diffusive model; Appendix V: Parametrization of boundaryscavenging processes; Appendix VI: Vertical, one-dimensional, one-and two-layer boundary scavenging models; Appendix VII: Theeffects of strong local scavenging; Appendix VIII. A two-dimen-sional ocean dispersion model; Appendix IX. A hybrid vertical scav-enging model; Appendix X. Estimation of concentra-tions in foodchains; References; Glossary; List of basic symbols used.


APPLICATION OF EXEMPTION PRINCIPLES TO THE RECYCLE AND REUSE OF MATERIALS FROM NUCLEAR FACILITIES: A Safety PracticeSafety Series No. 111-P-1.1

This Safety Practices publication, a part of the lAEA’s RadioactiveWaste Safety Standards (RADWASS) programme, provides guid-ance on those application of internationally agreed principles fordetermining those levels of radionuclides in materials below whichthey can be exempted from regulatory control and can be recycledor reused without any further restriction. lt illustrates a methodologyby which practical exempt quantities for the recycle and reuse ofthese materials may be derived and gives typical exempt valuesbased on a generic assessment.

Contents: 1. Introduction; 2. Exemption from regulatory controlapplied to recycle and reuse; 3. Recycle and reuse as options;4. Methods for dose assessment; 5. Recycle scenarios and relatedassumptions; 6. Derived exemption levels; 7. Additional considera-tions and discussion of the results; 8. Summary; References; Appen-dix I. Methods for estimating individual and collective doses fromexternal exposures to radionuclides during recycle and reuse;Appendix II. Methods for estimating individual and collective dosesfrom inhalation and ingestion of radioactive materials; Appendix III.Estimated individual and collective effective dose equivalents byscenario and pathway for concentrations of 1 Bq/g of each referenceradionuclide for the recycle and reuse of contaminated materials.


ASSESSING THE IMPACT OF DEEP SEA DISPOSAL OF LOW LEVEL RADIOACTIVE WASTE ON LIVING MARINE RESOURCESTechnical Reports Series No. 288

In revising the definition of high level radioactive waste unsuitablefor dumping at sea, calculations of water concentrations in and neara dump site have been made and used to estimate doses to ‘typical’marine species living at or near the sea floor at a depth of 4000 m.These calculations show that there are radionuclides that can giverise to significant doses to these typical species and that future revi-sions of the Definition and Recommendations under the Conventionon the Prevention of Marine Pollution by Dumping of Wastes andOther Matter will have to consider impacts on the marine ecosystemin setting limits for dumping.


73

Contents: 1. Introduction; 2. Nature of the deep sea ecosystem;3. Naturally occurring and fallout radionuclides in the marine envi-ronment; 4. Effects of radiation on aquatic organisms; 5. Methods ofdosimetry for aquatic organisms and an estimate of the backgrounddose rate in the deep sea; 6. Derivation of dose rates to organismsbased on the IAEA definition of high level radioactive waste unsuit-able for dumping at sea; 7. Dose rates arising from actual seadumping operations; 8. Summary and conclusions; Appendix: Equa-tions and parameters used for calculations and results.


DEFINITION AND RECOMMENDATIONS FOR THE CONVENTION ON THE PREVENTION OF MARINE POLLUTION BY DUMPING OF WASTES AND OTHER MATTER, 1972–1986 Edition: A Safety GuideSafety Series No. 78

Under the terms of the Convention on the Prevention of MarinePollution by Dumping of Wastes and Other Matter, the IAEA is theorganization with the responsibility for defining high level radioac-tive wastes or other high level radioactive matter which is unsuitablefor dumping at sea. The IAEA established a provisional Definitionand Recommendations in 1972 and a revised version in 1978. Thepresent Safety Series document contains the second revised Defini-tion and Recommendations, which were established in 1985.

Contents: Scope; 1. Introduction to the Definition and Recom-mendations; 2. Definition of high level radioactive waste or otherhigh level radioactive matter unsuitable for dumping at sea;3. Recommendations required by Annex II of the Conventionpertaining to the dumping of radioactive wastes; Annex I. Derivationof the quantitative definition of wastes unsuitable for dumping atsea; Annex II. Comparison with previous Definition and Recom-mendations; Annex III. Summary of meetings and documentation.


DESIGN AND OPERATION OF HIGH LEVEL WASTE VITRIFICATION AND STORAGE FACILITIESTechnical Reports Series No. 339

This report gives an up to date review of high level waste vitrifica-tion and storage facilities currently in an advanced stage ofimplementation.

Contents: 1. Introduction; 2. HLLW; 3. Solidification processes;4. Current vitrification processes; 5. Glass canister handling proce-dures generally implemented in the vitrification plants; 6. Safetyconsiderations; 7. Summary.


DESIGN AND OPERATION OF RADIOACTIVE WASTE INCINER-ATION FACILITIESSafety Series No. 108

The purpose of this safety guide is to provide safety guidance for thedesign and operation of radioactive waste incineration facilities. Theguide emphasizes the design objectives and system requirements to

be met and provides recommendations for the procedure of processselection and equipment design.

Contents: 1. Introduction; 2. Design and operational objectives;3. Basic safety aspects; 4. System requirements; 5. Conceptualdesign; 6. Subsystem requirements; 7. Component requirements;8. Controls and instrumentation; 9. Building and physical arrange-ment; 10. System testing and commissioning; 11. System operation;12. Documentation; Annex I: Waste source and characteristics;Annex II: Basic incineration concepts; Annex III: Basic off-gastreatment concepts.




ESTABLISHING A NATIONAL SYSTEM FORRADIOACTIVE WASTE MANAGEMENT:A Safety StandardSafety Series No. 111-S-1

The objective of this Safety Standard is to assist in developing anational system for radioactive waste management, to identify thekey responsibilities of the parties involved and to delineate essentialfeatures of such a system. The document encompasses all aspects ofradioactive waste management from waste minimization to disposal.It details the responsibilities of Member States, regulatory bodiesand operators, and describes other important features such asprocesses for safety, environmental impact assessment and licens-ing. It is based on the principles set out in the RADWASS SafetyFundamentals document, Safety Series No. 111-F.

Contents: 1. Introduction; 2. Objective and principles of radioactivewaste management; 3. National framework for radioactive wastemanagement; 4. Responsibilities associated with radioactive wastemanagement; 5. Important features of radioactive waste manage-ment; Annex: Basic steps in radioactive waste management.

STI/PUB/990 (28 pp., 1 figure; 1995)E ISBN 92–0–103495–4C ISBN 92–0–502396–5F ISBN 92–0–200296–7R ISBN 92–0–405495–6S ISBN 92–0–304995–9Price: 160 Austrian schillings (€11.63)

FACTORS RELEVANT TO THE RECYCLING OR REUSE OF COMPONENTS ARISING FROM THE DECOMMISSIONING AND REFURBISHMENT OF NUCLEAR FACILITIESTechnical Reports Series No. 293

The decommissioning and decontamination of nuclear facilities is atopic of interest because of the large number of older nuclear facil-ties which are, or soon will be, retired from service. This publicationprovides a review of the engineering, social, scientific and adminis-trative factors relevant to the safe recycling or reuse of componentsarising from decommissioning or refurbishment of nuclear facilities.

Contents: 1. Introduction; 2. Scope; 3. Recycling in industry;4. Recycling or reuse of nuclear components; 5. Decontaminationfor recycling or reuse; 6. Factors to be considered in the recycling or

R A D I O A C T I V E W A S T E M A N A G E M E N T

74

reuse of components; 7. Life extension of facilities; 8. Safety inrecycling or reuse; Summary and conclusions; Annex. Monitoringfor compliance with release criteria.

STI/DOC/10/293 (75 pp., 17 figures; 1988)ISBN 92–0–125888–7Price: 250 Austrian Schillings (€18.17)


(See under Waste Repositories, p. 56)

MANAGEMENT OF ABNORMAL RADIOACTIVE WASTES AT NUCLEAR POWER PLANTSTechnical Reports Series No. 307


MANAGEMENT OF LOW AND INTERMEDIATE LEVELRADIOACTIVE WASTES 1988Proceedings Series

Proceedings of a symposium jointly organized with the CEC, Stock-holm, Sweden, 16–20 May 1988. The symposium addressed allmain stages in the management of radioactive wastes, namely treat-ment, conditioning, waste form characterization and disposal. At thesymposium the substantial progress in the development of thesesystems was indicated. In this context the construction of a deeprepository with complementary regulatory arrangements in Swedenwas an important milestone in the establishment of waste manage-ment facilities. The various contributions represent a wide spectrumof problems associated with the management of radioactive wastesin different countries, describe national waste management policiesin Member States, and present new ideas, approaches and problems,for example problems of management of mixed hazardous wasteswhich contain not only radioactive materials but also other chemi-cally hazardous or aggressive non-radioactive components.

Contents: (Vol. 1) National and international waste managementprogrammes and policies; Disposal options and performance andsafety assessment; Waste characterization, quality control andacceptance criteria; Treatment and conditioning of solid wastes(including volume reduction); Treatment and conditioning of mixedhazardous wastes and institutional wastes; (Vol. 2) Treatment andconditioning of liquid wastes; Disposal and safety assessment;Waste characterization and acceptance criteria; Treatment andconditioning of radioactive wastes.

STI/PUB/784 (Vol. 1: 459 pp., 92 figures; Vol. 2: 314 pp., 73 figures; 1989)1: ISBN 92–0–020089–32: ISBN 92–0–020189–XPrice: Vol. 1: 1370 Austrian schillings (€99.56)


MANAGEMENT OF SEVERELY DAMAGED NUCLEAR FUEL AND RELATED WASTETechnical Reports Series No. 321

This report provides a comprehensive review of managementinsights and principles on on-site, post-accident activities at nuclearpower plants experiencing significant fuel damage. It combinesinformation on emergency response procedures and off-site planswith a discussion of on-site experience. lt provides a reference texton the requirements that arise after the critical phase of emergencyresponse.

Contents: 1. Introduction; 2. Strategic planning; 3. Stabilizing thefuel; 4. Data management and analysis; 5. Initial waste manage-ment; 6. Initial decontamination; 7. Fuel removal; 8. Fuel condi-tioning, transport and interim storage; 9. Abnormal waste; Condi-tioning to disposal; 10. Preparation for the decommissioning of fueldamaged plants; 11. Conclusions; Annex A: Nuclear Power PlantA-1 (Czechoslovakia) experience.


METHODOLOGY AND TECHNOLOGY OF DECOMMISSIONING NUCLEAR FACILITIESTechnical Reports Series No. 267

This report is a review of the current state of the methodology andtechnology of decommissioning nuclear facilities including remotesystems technology.

Contents: Introduction; Scope; Definitions of the basic stages ofdecommissioning; Consideration affecting decommissioningchoices; Methodology and technology of decommissioning;Decommissioning safety; Facilitation of decommissioning; Infor-mation database; Conclusions and recommendations: Annex A:Inventory of nuclear facilities of interest to decommissioning;Annex B: Disassembly techniques; Annex C: Remotely controlledequipment for decommissioning.


METHODS FOR REDUCING OCCUPATIONAL EXPOSURES DURING THE DECOMMISSIONING OF NUCLEAR FACILITIESTechnical Reports Series No. 278


OPERATIONAL MANAGEMENT FOR RADIOACTIVE EFFLUENTS AND WASTES ARISING IN NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-O11


PRINCIPLES FOR THE EXEMPTION OF RADIATION SOURCES AND PRACTICES FROM REGULATORY CONTROLSafety Series No. 89


SAFE MANAGEMENT OF WASTES FROM THE MINING AND MILLING OF URANIUM AND THORIUM ORES:Code of Practice and Guide to the CodeSafety Series No. 85

This publication is an update of IAEA Safety Series No. 44,published in 1976, necessitated by a number of developments in the


75

technical and regulatory aspects of the management of wastes result-ing from the mining and milling of uranium and thorium ores. Itconsists of two parts: a Code of Practice (Part I) and a Guide to theCode (Part II). The Code sets forth the requirements for the safe andresponsible handling of the wastes, while the Guide presents furtherguidance in the use of the Code together with some discussion of thetechnology and concepts involved.

Contents: Part 1. Code of Practice: 1. Introduction; 2. Objective;3. Scope; 4. Definitions; 5. Wastes from the mining and milling ofradioactive ores, their radiological impact and control bywaste management; 6. Principles of radiological protection;7. Responsibilities; 8. Design of waste management facilities;9. Collection, storage and treatment of wastes; 10. Operation ofwaste management facilities; 11. Decommissioning of mines, millsand waste management facilities; 12. Monitoring, surveillance andmaintenance. Part 2. Guide to the Code: 1. Introduction; 2. Objec-tive; 3. Scope; 4. Definitions; 5. Wastes from the mining and millingof radioactive ores, their radiological impact and control by wastemanagement; 6. Principles of radiological protection; 7. Responsi-bilities; 8. Design of waste management facilities; 9. Collection,storage and treatment of wastes; 10. Operation of waste manage-ment facilities; 11. Decommissioning of mines, mills and wastemanagement facilities; 12. Monitoring, surveillance and mainte-nance; References.

STI/PUB/772 (70 pp., 2 figures; 1987)E ISBN 92–0–123587–9F ISBN 92–0–224188–0R ISBN 92–0–423689–2S ISBN 92–0–323488–8Price: 260 Austrian schillings (€18.89)

SAFETY ASSESSMENT FOR SPENT FUEL STORAGE FACILITIESSafety Series No. 118

This Safety Practice has been developed through a series of techni-cal meetings and addresses the management of all issues relevant tothe safe storage of spent fuel from nuclear power plants. Comple-menting Safety Series No. 116, Design of Spent Fuel Storage Facil-ities, and Safety Series No. 117, Operation of Spent Fuel StorageFacilities, it describes accepted international approaches for main-taining fuel subcritical, removing residual heat, providing radiationprotection and containing radioactive materials for the lifetime ofthe facility. It is primarily intended to provide details on the safetyassessment of interim spent fuel storage facilities that are not anintegral part of an operating nuclear power plant.

Contents: 1. Introduction; 2. Safety assessment; 3. Safety assess-ment of operational states; 4. Safety assessment of accidents; 5.Safety Analysis Report; Annex: Contents of a Safety AnalysisReport.


SAFETY PRINCIPLES AND TECHNICAL CRITERIA FOR THE UNDERGROUND DISPOSAL OF HIGH LEVEL RADIOACTIVE WASTESSafety Series No. 99


SITING OF GEOLOGICAL DISPOSAL FACILITIES: A Safety GuideSafety Series No. 111-G-4.1

This safety guide, published under the IAEA’s Radioactive WasteSafety Standards (RADWASS) programme, defines the process tobe used and guidelines to be considered in selecting sites for deepgeological disposal of radioactive wastes. It also addresses thesocial, economic and environmental factors to be considered in siteselection. All data needed for the application of the guidelines arealso specified.

Contents: 1. Introduction; 2. Safety approach; 3. The siting process;4. Site selection guidelines and data needs; Glossary.

STI/PUB/952 (32 pp.; 1994)ISBN 92–0–101294–2Price: 180 Austrian schillings €(13.08)

THE PRINCIPLES OF RADIOACTIVE WASTE MANAGEMENT:A Safety FundamentalSafety Series No. 111-F

This Safety Fundamentals document should serve as a guide andshould complement national standards and criteria in the develop-ment of radioactive waste management programmes in MemberStates. It encompasses all aspects of radioactive waste managementfrom waste minimization to disposal and sets out objectives andprinciples for the protection of human health and the environment,present and future.

Contents: 1. Introduction; 2. Objective of radioactive waste mana-gement; 3. Fundamental principles of radioactive waste mana-gement; Annex: Basic steps in radioactive waste management.

STI/PUB/989 (24 pp., 1 figure; 1995)E ISBN 92–0–103595–0C ISBN 92–0–502296–9F ISBN 92–0–200196–0R ISBN 92–0–405395–XS ISBN 92–0–304995–9Price: 160 Austrian schillings (€11.63)


The IAEA Safety Standards Series comprises publications of aregulatory nature covering nuclear safety, radiation protection,radioactive waste management, the transport of radioactive materi-als, the safety of nuclear fuel cycle facilities and quality assurance.These publications are issued under the terms of Article III of theAgency’s Statute, which authorizes the Agency to establish stan-dards of safety for protection against ionizing radiation. The SafetyStandards Series supersedes the Safety Series, in which over 200publications were issued. Safety Standards Series publications arecategorized into:




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WASTE SAFETYNear Surface Disposal of Radioactive Waste

NEAR SURFACE DISPOSAL OF ➜NEWRADIOACTIVE WASTE: Safety RequirementsSafety Standards Series No. WS-R-1

This Safety Requirements publication sets out the basic safetyrequirements related to the disposal of radioactive wastes in nearsurface repositories. As a Safety Requirements publication it issupported by a number of associated Safety Guides which provideguidance on the implementation of the requirements. Its principlesare derived from the Safety Fundamentals publication, Safety SeriesNo. 111-F, The Principles of Radioactive Waste Management. Itincludes requirements for the protection of human health, for theassessment procedures needed to ensure that safety is achieved, andtechnical requirements for waste acceptance and for siting, design,construction, operation and closure of the repository as well as forthe post-closure phase.

Contents: 1. Introduction; 2. Requirements for the protection ofhuman health and the environment; 3. Safety assessment andcompliance with safety requirements; 4. Organizational and techni-cal safety requirements; 5. Waste acceptance requirements; 6. Char-acteristics of an acceptable site; 7. Design of disposal facilities;8. Construction; 9. Operation; 10. Closure; 11. Post-closure phase;12. Quality assurance; Annex: Dose and risk criteria for the post-closure phase.


STI/PUB/1073 (29 pp., 1999)ISBN 92–0–101099–0Price: 170 Austrian schillings (€12.35)Safety Guides

SAFETY ASSESSMENT FOR NEAR SURFACE ➜NEWDISPOSAL OF RADIOACTIVE WASTE: Safety GuideSafety Standards Series No. WS-G-1.1

This Safety Guide provides recommendations on how to meet therequirements related to safety assessment in the Safety Require-ments publication, Safety Standards Series No. WS-R-1, NearSurface Disposal of Radioactive Waste (1999). It addresses thesubject of safety assessment for near surface disposal of radioactivewaste and provides guidance on approaches to performing safetyassessments in the context of near surface repositories.

Contents: 1. Introduction; 2. General considerations for safetyassessment; 3. Guidelines for safety assessment; 4. Confidencebuilding.



Predisposal Management of RadioactiveWaste, Including Decommissioning

DECOMMISSIONING OF ➜NEWNUCLEAR POWER PLANTS AND RESEARCH REACTORS: Safety GuideSafety Standards Series No. WS-G-2.1

This Safety Guide addresses the subject of how to meet the require-ments for decommissioning of nuclear power plants and researchreactors laid down in the Safety Requirements publication, SafetyStandards Series No. WS-R-2, Predisposal Management ofRadioactive Waste, Including Decommissioning. It provides guid-ance to national authorities and operating organizations on theplanning and safe management of the decomissioning of suchinstallations.

Contents: 1. Introduction; 2. Key issues specific to decommission-ing; 3. Selection of a decommissioning option; 4. Facilitatingdecommissioning; 5. Planning and safety assessment for decommis-sioning; 6. Critical tasks of decommissioning; 7. Managementduring decommissioning; 8. Completion of decommissioning;References; Annex I: Example of the contents of a final radiologicalsurvey report; Annex II: Example of documented plans and manage-ment systems for implementation of decommissioning.


STI/PUB/1079 (41 pp., 1999)ISBN 92–0–102599–8Price: Austrian Schillings 200.00 (€14.35)

DECOMMISSIONING OF MEDICAL, ➜NEWINDUSTRIAL AND RESEARCH FACILITIES: Safety GuideSafety Standards Series No. WS-G-2.2

This Safety Guide addresses the subject of how to meet therequirements for the decommissioning of medical, industrial andresearch facilities where radioactive materials and sources areproduced, received, used and stored, as laid down in the SafetyRequirements publication, Safety Standards Series No. WS-R-2,Predisposal Management of Radioactive Waste, Including Decom-missioning. It provides guidance to national authorities and oper-ating organizations, particularly to those in developing countries(as such facilities are predominant in these countries), on theplanning and safe management of the decommissioning of suchfacilities.

Contents: 1. Introduction; 2. Key issues specific to decommission-ing; 3. Decommissioning options; 4. Facilitating decommissioning;5. Planning and safety assessment for decommissioning; 6. Criticaltasks of decommissioning; 7. Management during decommission-ing; 8. Completion of decommissioning; References; Annex I:Example of the contents of a decommissioning plan; Annex II:Safety assessment specific for decommissioning; Annex III:Example of the contents of a final radiation survey report.




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Safety Analysis

AN OCEANOGRAPHIC MODEL FOR THE DISPERSION OF WASTES DISPOSED OF IN THE DEEP SEATechnical Reports Series No. 263


ASSESSING THE IMPACT OF DEEP SEA DISPOSAL OF LOW LEVEL RADIOACTIVE WASTE ONLIVING MARINE RESOURCESTechnical Reports Series No. 288


DEFENCE IN DEPTH IN NUCLEAR SAFETY — ➜NEWA Report by the International Nuclear Safety Advisory GroupINSAG Series No. 10

(See under Nuclear Power Plants, INSAG Series, p. 28)

EFFECTS OF IONIZING RADIATION ON PLANTS AND ANIMALS AT LEVELS IMPLIED BY CURRENT RADIATION PROTECTION STANDARDSTechnical Reports Series No. 332


ELECTRICITY AND THE ENVIRONMENTProceedings Series

Proceedings of a senior expert symposium jointly organized byCEC, CMEA, ECE, IAEA, IEA, IIASA, OECD/NEA, UNEP,IBRO, WHO and WMO in co-operation with the Government ofFinland, Helsinki, Finland, 13–17 May 1991. The objective of thesymposium was to provide a comprehensive assessment of the envi-ronmental and health factors as well as the economic factorsinvolved in supplying electricity services, and to suggest a frame-work within which these issues should be taken into account inmaking future plans and decisions on electricity production and use.The potential role of different ways of meeting electricity servicerequirements was also analysed, taking into consideration bothdemand side and supply options in the light of their comparativeeconomic, environmental and health related impacts.

Contents: Opening session; Energy and electricity supply anddemand: Implications for the global environment; Energy sourcesand technologies for electricity generation; Comparativeenvironmental and health effects of different energy systems forelectricity generation; Incorporation of environmental and healthimpacts into policy, planning and decision making for the electricitysector; Luncheon sessions; Policy aspects of electricity and the envi-ronment; Key issues and findings and round table on challenges forinternational co-operation.


ENVIRONMENTAL CONTAMINATION FOLLOWING A MAJOR NUCLEAR ACCIDENTProceedings Series

Proceedings of a symposium jointly organized with FAO, UNEP andWHO, Vienna, 16–20 October 1989. Scientific research on the after-

effects of the Chernobyl accident on the environment and on humanhealth has provided new data pertaining to large scale contamina-tion. Papers at the symposium covered a wide range of subjects,including monitoring of radioactive contaminants in the environ-ment, levels of radioactive contamination of farmland, agriculturalcrops and dairy products in subsequent years, and methods for mini-mizing contamination of feed and food.

Contents: Vol. 1: Part I: Radioactive contamination of the envi-ronment: (a) General; (b) Air; (c) Soil; (d) Water; Part II: Monitor-ing of radioactivity: (a) General; (b) Strategies and policy; (c)Methods and techniques. Vol. 2: Part III: Radioactive contaminationof agricultural land and agricultural produce; Part IV: Countermea-sures to reduce radionuclide contamination of food chains; Part V:Radiation exposure of populations; Part VI: Radionuclides and inter-national trade in food; Special Session: Hot particles; Summary ofthe symposium: Important issues with significance for the future.

STI/PUB/825 (Vol. 1: 497 pp., 144 figures; Vol. 2: 451 pp., 70 figures;1990)1: ISBN 92–0–020090–72: ISBN 92–9–020190–3Price: Vol. 1: 1340 Austrian schillings (€97.38)


EVALUATING THE RELIABILITY OF PREDICTIONS MADEUSING ENVIRONMENTAL TRANSFER MODELS: A Safety PracticeSafety Series No. 100

This safety practice publication provides guidance on the availablemethods for evaluating the reliability of environmental transfermodel predictions. It provides a practical introduction to the subject,and particular emphasis has been given to worked examples in thetext. It is Intended to supplement existing IAEA publications onenvironmental assessment methodology. Although the bookaddresses the subject of environmental dose assessment, themethods described are of general application and are equally usefulin other areas where modelling techniques are applied.

Contents: 1. Introduction; 2. General aspects of model reliabilityevaluation; 3. Practical approaches to the evaluation of model relia-bility; Appendix I: Statistical equations; Appendix II: Latin hyper-cube sampling; Appendix III: Examples of parameter uncertaintyanalyses; Glossary.


HANDBOOK OF PARAMETER VALUES FOR THE PREDICTION OF RADIONUCLIDE TRANSFER IN TEMPERATE ENVIRONMENTSTechnical Reports Series No. 364

This handbook has been produced in collaboration with the Interna-tional Union of Radioecologists. It should serve as a convenient andauthoritative reference for radionuclide transfer parameter valuesused in biospheric assessment models. It supplements Safety SeriesNo. 57 (1982), ‘‘Generic Models and Parameters for Assessing theEnvironmental Transfer of Radionuclides from Routine Releases’’.

Contents: 1. Introduction; 2. Agricultural systems — vegetation;3. Agricultural systems — milk, meat and eggs; 4. Freshwaterecosystems — fish; 5. Natural ecosystems; 6. Food processing trans-fer parameters.


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HUMAN RELIABILITY ANALYSIS IN PROBABILISTIC SAFETY ASSESSMENT FOR NUCLEAR POWER PLANTSSafety Series No. 50-P-10


NATURAL ANALOGUES IN PERFORMANCE ASSESSMENTSFOR THE DISPOSAL Of LONG LIVED RADIOACTIVE WASTESTechnical Reports Series No. 304


PROCEDURES FOR CONDUCTING PROBABILISTIC SAFETYASSESSMENTS OF NUCLEAR POWER PLANTS (LEVEL 2):Accident Progression, Containment Analysisand Estimation of Accident Source TermsSafety Series No. 50-P-8


PROCEDURES FOR CONDUCTING ➜NEWPROBABILISTIC SAFETY ASSESSMENTS OF NUCLEAR POWER PLANTS (LEVEL 3): Off-Site Consequences and Estimation of Risks to the PublicSafety Series No. 50-P-12


RADIONUCLIDE SOURCE TERMS FROM SEVERE ACCIDENTS TO NUCLEAR POWER PLANTS WITH LIGHT WATER REACTORS — A Report by the International Nuclear Safety Advisory Group Safety Series No. 75-INSAG-2


REACTIVITY ACCIDENTSTechnical Reports Series No. 354


SEVERE ACCIDENTS IN NUCLEAR POWER PLANTSProceedings Series


SOURCE TERM EVALUATION FOR ACCIDENT CONDITIONSProceedings Series


SUMMARY REPORT ON THE POST-ACCIDENT REVIEWMEETING ON THE CHERNOBYL ACCIDENT — A Report by the International Nuclear Safety Advisory GroupSafety Series No. 75-INSAG-1


THE CHERNOBYL ACCIDENT: UPDATING OF INSAG-1 — A Report by the International Nuclear Safety AdvisoryGroup Safety Series No. 75-INSAG-7


THE INTERNATIONAL CHERNOBYL PROJECT Assessment of Radiological Consequences and Evaluation of Protective Measures: Reports by an International Advisory Committee

THE INTERNATIONAL CHERNOBYL PROJECT: An Overview

THE INTERNATIONAL CHERNOBYL PROJECT: Technical Report

THE INTERNATIONAL CHERNOBYL PROJECT:Proceedings of an International Conference

(See under Radiation Protection, pp. 66–67)

THE ROLE OF PROBABILISTIC SAFETY ASSESSMENT AND PROBABILISTIC SAFETY CRITERIA IN NUCLEAR POWER PLANT SAFETY Safety Series No. 106

This safety report establishes guidelines on the role that probabilis-tic safety assessment can play as part of an overall safety assuranceprogramme in nuclear power plants. It also describes a frameworkfor probabilistic safety criteria (PSC) and provides guidance for theestablishment of PSC values.

Contents: 1. Introduction; 2. The role of PSA; 3. PSA management,methodology and documentation; 4. Development of PSC; Refer-ences; Glossary.

STI/PUB/911 (27 pp., 1 figure; 1992) ISBN 92–0–101492–9Price: 160 Austrian schillings (€11.63)

TREATMENT OF EXTERNAL HAZARDS IN PROBABILISTICSAFETY ASSESSMENT FOR NUCLEAR POWER PLANTS Safety Series No. 50-P-7


USE OF PROBABILISTIC SAFETY ASSESSMENT FOR OPERATIONAL SAFETY — PSA ‘91 Proceedings Series

Proceedings of a symposium jointly organized with ANS, ENS andOECD/NEA, Vienna, 3–7 June 1991. During recent years the devel-opment of PSA has been directed towards its use as a practical toolfor the enhancement of operational safety. Only plant specific analy-sis can provide a basis for meaningful risk management. The impor-tance of human interventions in the recovery from degraded states ofoperation, the importance of inclusion of external events in PSA, thedetermination of potentials for common cause failures and theimportance of treating and communicating the uncertainties havealready been well established within the PSA community. Also,


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risks during low power level and shutdown states have become morerecognized.

Contents: Opening remarks and invited papers; Methodology;Regulatory applications; PSA use and applications — Part I; Appli-cations to process facilities and international activities; Operatingexperience and ageing; PSA use and applications — Part II; PSAresults and insights — Part I; Common cause and external events;PSA results and insights — Part II; Human factors; Living PSA;PSA level 2 and level 3; Poster presentations; Summary, conclusionsand recommendations; Closing session.


Quality Management

IMPLEMENTATION OF QUALITY ASSURANCE CORRECTIVE ACTIONS: A Manual Technical Reports Series No. 317

This manual was developed to serve as guidance on non-conformance and corrective actions which have been identified asthe major problems in the implementation of an effective qualityassurance programme. The scope of this manual, while fullyaddressing the requirements in the governing NUSS programmedocuments, also covers corrective action processes which wouldmore generally assist users in developing good practices forimproved performance in all areas of safety, reliability and econom-ics, and it offers a practical model and illustrative examples of themeans by which effective measures and actions can be implemented.

Contents: 1. Introduction; 2. Description of corrective actionprocess; 3. Identification of deficiencies; 4. Assessing and correctingdeficiencies; 5. Root cause analysis; 6. Verification and follow-up;7. Implementing procedures; 8. Trend analysis; 9. Summary; Defin-itions; Annex A: Example of a hold for QA clearance tag; Annex B:Examples of non-conformance report forms; Annex C: Example ofa reject tag; Annex D: Example of a checklist for reviewing non-conformance dispositions; Annex E: Examples of a stop work noticeand stop work notice tag; Annex F: Examples of a deficiency reportform and deficiency report–work order forms; Annex G: Example ofa list defining a significant event for a nuclear power plant;Annex H: Example of a method for evaluating personnel causeddeficiencies; Annex I: Example of a procedure for escalation tohigher levels of management to achieve corrective action; Annex J:Example of a status report for corrective actions; Annex K: Exampleof a non-conformance control implementing procedure; Annex L:Example of a corrective action request implementing procedure;Annex M: Example of an implementing procedure on tracking andtrending of quality problems; Annex N: Example of a method ofcoding of non-conformance data for defect analysis; Annex O:Example of reports available from a defect analysis programme.




QUALITY ASSURANCE FOR THE SAFE TRANSPORT OF RADIOACTIVE MATERIAL Safety Series No. 113

(See under Transport of Radioactive Material, p. 54)

QUALITY MANAGEMENT FOR NUCLEAR POWER PLANT OPERATION: A Manual Technical Reports Series No. 315


REGULATORY INSPECTION OF THE IMPLEMENTATION OF QUALITY ASSURANCE PROGRAMMES: A Manual Technical Reports Series No. 296

Guidance in the organization and performance of regulatory inspec-tion functions regarding the implementation of quality assuranceprogrammes in all stages of the nuclear power plant project. Themanual is intended primarily for the management personnel andupper staff from regulatory bodies, but it will also be helpful tomanagement personnel from nuclear utilities and vendors.

Contents: 1. Introduction; 2. Techniques and methods of inspection;3. Performance of regulatory inspections of quality assuranceprogrammes; 4. Inspection reports; 5. Periodic evaluation of effec-tiveness of and trends in quality assurance programme performance;6. Enforcement of compliance with the quality assuranceprogramme; 7. Manpower requirements and technical qualificationsof quality assurance regulatory inspectors; Appendix I: Inspectionprocedure on document control; Appendix II: Inspection procedureon procurement control; Appendix III: Inspection procedure onreceipt, storage and handling of materials and equipment; Appen-dix IV: Inspection procedure on control of measuring and test equip-ment; Appendix V: Inspection procedure on non-conformancecontrol; Appendix VI: Inspection procedure on corrective action;Appendix VII: Inspection procedure on record system;Appendix VIII: Inspection procedure on auditing; Annex I: Exampleof inspection report cover page for licensee inspection; Annex II:Example of inspection report cover page for vendor inspection;Annex III: Example of legal framework for enforcement measures;Annex IV: Example of severity level categorization for enforcementpurposes; Annex V: Example of a system of civil penalties forenforcement purposes.

STI/DOC/10/296 (132 pp.; 1989)ISBN 92–0–155089–7 Price: 400 Austrian schillings (€29.07)

Legal and Governmental Aspects

GUIDANCE FOR REGULATION OF UNDERGROUND REPOSITO-RIES FOR DISPOSAL OF RADIOACTIVE WASTES Safety Series No. 96


CODE ON THE SAFETY OF NUCLEAR POWER PLANTS: GOVERNMENTAL ORGANIZATION Safety Series No. 50-C-G (Rev. 1)


Q U A L I T Y M A N A G E M E N T — L E G A L A N D G O V E R N M E N T A L A S P E C T S

80

QUALIFICATIONS AND TRAINING OF STAFF OF THE REGULATORY BODY FOR NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-G1


INFORMATION TO BE SUBMITTED IN SUPPORT OF LICENSING APPLICATIONS FOR NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-G2


CONDUCT OF REGULATORY REVIEW AND ASSESSMENT DURING THE LICENSING PROCESS FOR NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-G3


INSPECTION AND ENFORCEMENT BY THE ➜NEWREGULATORY BODY FOR NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-G4 (Rev. 1)


PREPAREDNESS OF PUBLIC AUTHORITIES FOR EMERGENCIES AT NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-G6


LICENCES FOR NUCLEAR POWER PLANTS: CONTENT, FORMAT AND LEGAL CONSIDERATIONS: A Safety Guide Safety Series No. 50-SG-G8


REGULATIONS AND GUIDES FOR NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-G9


RADIATION PROTECTION INFRASTRUCTUREProceedings Series


REGULATORY PRACTICES AND SAFETY STANDARDS FORNUCLEAR POWER PLANTS Proceedings Series


STRENGTHENING RADIATION AND NUCLEAR SAFETY INFRASTRUCTURES IN COUNTRIES OF THE FORMER USSR

Proceedings of a forum organized by UNDP and the IAEA, Vienna,4–7 May 1993. These proceedings represent the first step of the UNproject to provide to the countries of the former USSR an integratedpackage of assistance to strengthen the overall national infrastruc-ture for radiation protection as well as for nuclear safety, includingthe establishment of an adequate legal framework.

Contents: Opening speeches; Presentations and discussions; Reportof the Joint Secretariat.

STI/PUB/939 (143 pp., 6 figures; 1993) E ISBN 92–0–102793–1 R ISBN 92–0–400493–2 Price: 300 Austrian schillings (€21.80)


NUCLEAR POWER


Proceedings of a Senior Expert symposium jointly organized byCEC, CMEA, ECE, IAEA, IEA, IIASA, OECD/NEA, UNEP,IBRO, WHO, and WMO, in co-operation with the Government ofFinland, Helsinki, 13–17 May 1991. The objective of the sympo-sium was to provide a comprehensive assessment of theenvironmental and health factors as well as the economic factorsinvolved in supplying electricity services, and to suggest a frame-work within which these issues should be taken into account inmaking future plans and decisions on electricity production and use.The potential role of different ways of meeting electricity servicerequirements was also analysed, taking into consideration bothdemand side and supply options in the light of their comparativeeconomic, environmental and health related impacts.

Contents: Opening session; Energy and electricity supply anddemand: Implications for the global environment; Energy sourcesand technologies for electricity generation; Comparative environ-mental and health effects of different energy systems for electricitygeneration; Incorporation of environmental and health impacts intopolicy, planning and decision making for the electricity sector;Luncheon sessions; Policy aspects of electricity and the environ-ment; Key issues and findings and round table on challenges forinternational co-operation.


NUCLEAR POWER PERFORMANCE AND SAFETYProceedings Series

Proceedings of a conference, Vienna, 28 September to2 October 1987. These proceedings provide an authoritative andcomprehensive picture of the current status of and trends in nuclearpower, nuclear safety and the nuclear fuel cycle.

Vol. 1: Performance, Overview and ProspectsIntroduction; Summaries of the Conference; The prospectsfor nuclear power in the 1990s; The need for safety innuclear power programmes; Performance of nuclear powerplants: Outlook for the future; Nuclear power economicsand financing.


Vol. 2: Achievements in Construction and OperationPlant construction achievements; Plant availability achieve-ments; Controlling and financing nuclear power costs;Achievements in technology transfer and infrastructuredevelopment; Advanced systems.


Vol. 3: Safety and International Co-operationThe need for safety in nuclear power programmes; Interna-tional co-operation in nuclear safety; Technical aspects inplant safety; Approaches to safety; Panel: Operationalsafety in the 1990s.


Vol. 4: Safety TechnologyNuclear safety experience and safety assessment trends;Safety and severe accidents; Safety improve-ments indesign and operation; Poster presentations.


Vol. 5: Nuclear Fuel CycleWaste management in the 1990s; Decontamination anddecommissioning; Waste management, treatment anddisposal; Nuclear fuel cycle — present and future; Enrich-ment services and advanced reactor fuels; Improvements inreactor fuel utilization and perfor-mance; Spent fuelmanagement options: Future needsand economic choices.


Vol. 6: Indexes and ListsContents of all volumes; List of participants; Author andtransliteration indexes; Index of papers and posters bynumber.


NUCLEAR POWER REACTORS IN THE WORLD — ➜NEWApril 1999 EditionReference Data Series No. 2

This is the nineteenth edition of Reference Data Series No. 2, whichpresents the most recent reactor data available to the Agency. Itcontains summarized information as of the end of 1998 on: (1)power reactors operating or under construction, and shut down; and(2) performance data on reactors operating in the Agency’s Member

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States, as reported to the Agency. The information is collected by theAgency through questionnaires circulated to Member States bymeans of the designated national correspondents. The replies areused to maintain the Agency’s Power Reactor Information System(PRIS).

IAEA-RDS-2/19 (78 pp., 6 figures, 9.5 × 17.5 cm; 1999)ISBN 92–0–101599–2Price: 140 Austrian schillings (€10.17)

THE NUCLEAR POWER OPTION Proceedings Series

Proceedings of an international conference, Vienna, 5–8 September1994. The purpose of the conference was to discuss the present andfuture importance of the nuclear power option as a source for energybased on proven, accepted, economically competitive and environ-mentally benign technologies. The safe and reliable operation ofexisting nuclear power plants, the demonstration of convincing solu-tions to the storage and disposal of radioactive waste, a predictablelicensing process and supportive government policies are essentialprerequisites to achieving a wider public acceptance of nuclearpower, which presently is the most important factor deciding itsfuture application.

Contents: Plenary session; National and regional overviews; Learn-ing from experience: I. Operation and maintenance; II. Construc-tion, quality assurance and decommissioning; III. Improving perfor-mance; Issues affecting the nuclear power option: I. Public accep-tance; II. Irradiated fuel and waste management; III. Safety; IV.Economics, environment and liability; Timely preparation: I.Providing resources; II. Government strategies; Panel discussion;Closing statements.


Nuclear Power Planning and Economics

ADVANCED NUCLEAR POWER SYSTEMS: DESIGN, TECHNOLOGY, SAFETY AND STRATEGIES FOR THEIR DEVELOPMENTProceedings Series

Proceedings of a symposium organized by the IAEA and hosted bythe Korea Electric Power Corporation on behalf of the Governmentof the Republic of Korea, in co-operation with the CEC, the Euro-pean Nuclear Society, the Korea Atomic Industrial Forum, theKorean Nuclear Society, the OECD/NEA and the World EnergyCouncil, Seoul, 18–22 October 1993. The purpose of the sympo-sium was to provide a forum for discussions on the need for nuclearpower, on the features of advanced nuclear power systems and theirdesign objectives and safety approaches, taking into considerationthe views of regulatory bodies, on identifying barriers to the deploy-ment of these systems, and on reviewing options for internationalco-operation.

Contents: Opening session; Introduction and overviews of otherrelevant conferences; Design and safety objectives of advancednuclear power systems; Panel: Regulatory experience and views onsafety aspects of advanced reactors; Barriers and strategies for thedeployment of advanced nuclear power systems; Panel: Evaluationof barriers and strategies for the deployment of advanced nuclearpower systems; Options for international co-operation for thedeployment of advanced nuclear power systems; Panel: The role ofinternational organizations; Closing session.


BID INVITATION SPECIFICATIONS FOR NUCLEAR POWER PLANTS — A GuidebookTechnical Reports Series No. 275

This Guidebook constitutes a complement to a series of technicalguidebooks: Technical Evaluation of Bids for Nuclear Power Plants,Technical Reports Series No. 204 (1981); Guidebook on the Intro-duction of Nuclear Power, Technical Reports Series No. 217 (1982);and Economic Evaluation of Bids for Nuclear Power Plants, 1999Edition, Technical Reports Series No. 369 (2000). These provide, inparticular, information on the process of plant acquisition and adviceon the principal activities involved in the planning and implementa-tion of nuclear power projects, as well as on the infrastructurerequirements and development needs for the successful implemen-tation of a nuclear power programme. These reports are directed tothe special needs of developing countries.

Contents: Introduction; Part 1. Information provided by the owner;Part 2. Information requested from the bidders; Appendix A. IAEAAccount System for Nuclear Power Plants; Appendix B. Technicalquestionnaires; Appendix C. Abbreviations; Bibliography.

STI/DOC/10/275 (165 pp.; 1987)ISBN 92–0–155187–8Price: 500 Austrian schillings (€36.34)

CHOOSING THE NUCLEAR POWER OPTION: ➜NEWFACTORS TO BE CONSIDERED

This guide was prepared on the basis of experience gained withnuclear power programmes in Members States and the current real-ities of the world nuclear regime. It provides information on politi-cal, governmental, economic, financial, technical and safety issuesassociated with planning and implementing a nuclear powerprogramme. The main areas in which policies must be developed arehighlighted, as are the roles and responsibilities of the government,the plant owner and the national industry. This publication isintended to serve as a guide to decision makers and governmentsconsidering the introduction of nuclear power programmes.

Contents: 1. Introduction; 2. Nuclear power: Status and prospects;3. Nuclear safety and radiation protection; 4. Nuclear fuel cycle;5. Management of radioactive waste and decommissioning ofnuclear facilities; 6 Environmental aspects; 7. Legal and regulatoryaspects; 8. Financing of nuclear power; 9. Public acceptance andparticipation in decision making; 10. National policies of impor-tance to nuclear power development; 11. Conclusion.


ECONOMIC EVALUATION OF BIDS FOR ➜NEWNUCLEAR POWER PLANTS - 1999 EditionTechnical Reports Series No 396

This report is an update of Technical Reports Series No. 269,Economic Evaluation of Bids for Nuclear Power Plants; A Guide-book (1986). It contains state of the art information, advice andrecommendations on the different principles, methods and guide-lines which should be used and applied when conducting aneconomic evaluation of nuclear power plant bids. Annex I lists an

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improved IAEA cost account system for nuclear power plants andAnnex II describes the improved and updated software package foreconomic bid evaluation, BIEDVAL-3, which is more flexible anduser-friendly than the previous version and can be found on the CD-ROM accompanying this report.

Contents: 1. Introduction; 2. Outline of the complete bid evaluationprocess and description of the economic bid evaluation; 3. Contractapproaches; 4. Basis for the economic bid evaluation; 5. Evaluationmethods; 6. Sources of financing, financing proposals and aspects ofthe economic evaluation of financing proposals; 7. Implementationof the economic bid evaluation; 8. Technology transfer; Appendix I:Further considerations on evaluation methods; Appendix II: List oftypical bid documentation; Annex I: IAEA account system fornuclear power plants; Annex II: IAEA computer program foreconomic bid evaluation.

STI/DOC/010/396 (224 pp., 21 figures; 2000)ISBN 92-0-100400-1Price: 710 Austrian schillings ( 51.60)

ELECTRICITY, HEALTH AND THE ➜NEWENVIRONMENT: COMPARATIVE ASSESSMENT IN SUPPORT OF DECISION MAKINGProceedings Series

Proceedings of a symposium jointly organized by the EC, ESCAP,IAEA, IIASA, OECD/NEA, OPEC, UNEP, UNIDO, IBRD andWMO, Vienna, 16–19 October 1995. The symposium was convenedas part of the inter-agency joint project on databases and method-ologies for comparative assessment of different energy sources forelectricity generation (DECADES). Its objective was to enhance andstrengthen information sharing and co-operation between interestedand affected parties in the field of electricity demand analysis andsupply planning, aiming at implementing sustainable policies in thepower sector, taking into account economic, social, health and envi-ronmental aspects.

Contents: Opening session; Key issues in the decision makingprocess; Assessment of health and environmental impacts; Inte-grated frameworks for comparative assessment; Implementation ofcomparative assessment; Implementation of comparative assess-ment: Country case studies; Comparative assessment in decisionmaking; Poster presentations; Towards sustainable electricity poli-cies: Challenges for international co-operation (Summary of RoundTable).


ENERGY, ELECTRICITY AND NUCLEAR ➜NEWPOWER ESTIMATES FOR THE PERIOD UP TO 2020 — July 1999 EditionReference Data Series No. 1

This is the nineteenth edition of Reference Data Series No. 1,containing the most recent estimates of energy, electricity andnuclear power trends up to the year 2020. Nuclear data are based onactual statistical data collected by the IAEA’s Power Reactor Infor-mation System (PRIS). Energy, electricity and population data for1998 are estimates based on information from the Statistical Officeof the United Nations.

IAEA-RDS-1/19 (53 pp., 10 figures, 9.5 × 17.5 cm; 1999)ISBN 92–0–101899–1Price: 130 Austrian schillings (€9.45)

FINANCING ARRANGEMENTS FOR NUCLEAR POWER PROJECTS IN DEVELOPING COUNTRIES: A Reference BookTechnical Reports Series No. 353

This report outlines the general characteristics of financing a nuclearpower project and presents innovative approaches for power gener-ation financing. It discusses the special conditions and requirementsof nuclear power projects and their financing complexities. Theavailability of adequate and secure financial resources is one of themost crucial constraints in the implementation of nuclear powerprojects in developing countries. Possible ways and means ofdealing with these constraints are presented.

Contents: Chapter 1. Introduction; Chapter 2. The status of nuclearpower and special circumstances related to the financing of nuclearpower projects; Chapter 3. Costs and economic feasibility ofnuclear power plants; Chapter 4. Conventional approaches forfinancing power generation projects in developing countries;Chapter 5. Experience gained and lessons learned; Chapter 6. Alter-native approaches for mobilizing financial resources; Chapter7. Conclusions; References; Glossary; Annex I: Issues affecting thefinancing of nuclear power plants and the actions proposed forvarious actors; Annex II: Alternative Energy fund of Egypt; AnnexIII: Sector understanding on export credits for nuclear power plants;Annex IV: Aliaga thermal power project in Turkey; Annex V: BOTproject development cycle.


GUIDEBOOK ON RESEARCH AND DEVELOPMENT SUPPORT FOR NUCLEAR POWERTechnical Reports Series No. 298

This guidebook summarizes the experience of individual countrieson the role of the R&D organization in developing their nuclearpower programmes.

Contents: 1. Introduction; 2. The role of the R&D organization;3. Establishing the R&D organization; 4. Managing the R&D orga-nization; References; Appendix I: The role of R&D in developingCanada’s nuclear power programmes; Appendix II: Indian experi-ence in R&D activities for nuclear power; Appendix III: Spanishexperience in R&D activities for the nuclear power programme;Appendix IV: The United Kingdom Atomic Energy Authority andthe United Kingdom Nuclear Power Programme; Appendix V: TheElectric Power Research Institute and its nuclear R&Dprogramme.


HEALTH AND ENVIRONMENTAL IMPACTS OF ➜NEWELECTRICITY GENERATION SYSTEMS:PROCEDURES FOR COMPARATIVE ASSESSMENTTechnical Reports Series No. 394

The present report is intended to assist in the design and implemen-tation of comparative risk assessment studies for the estimation ofhealth and environmental impacts of various electricity generationoptions. It sets out the framework for carrying out such assessmentsand identifies the major technical issues and uncertainties in theassessment process.

Contents: 1. Introduction; 2. Impacts and impact assessment: Basicconcepts; 3. Methodological approach for estimating health andenvironmental impacts; 4. Calculation and use of impact indicators

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for comparative assessment; 5. Key methodological issues; Appen-dix I: Global climate change; Appendix II: Energy security.


NUCLEAR DESALINATION OF SEA WATER ➜NEWProceedings Series

Proceedings of a symposium on Desalination of Sea Water withNuclear Energy organized by the IAEA and hosted by KAERI onbehalf of the Government of the Republic of Korea in co-operationwith the Global Technology Centre and the International Desalina-tion Association and held in Teajon, 26–30 May 1997. The sympo-sium provided a forum for the review of the latest technologicalexperience, design and development of nuclear desalinationsystems, and their future prospects. Amongst the wide variety oftopics discussed were the activities carried out by some selectedorganizations and institutes, the experience gained in existingnuclear desalination plants and their facilities, national and bilateralprogrammes, including research, design and development, forecastsfor the future and the challenges that lie ahead.

Contents: Opening session: Opening statements; Overviews;National programmes and activities. Panel 1: The challenges ofinternational co-operation; Technical aspects; Desalination usingnuclear, fossil and other energy sources; Opportunities fordesalination systems using nuclear energy. Panel 2: Why are therenot more desalination plants using nuclear energy?


NUCLEAR POWER PROJECT MANAGEMENT: A GuidebookTechnical Reports Series No. 279

This guidebook provides specific advice and guidance to projectmanagement for the construction of nuclear power plants. Whileoperating performance of nuclear power plants has been improvingin recent years and has generally been comparable to or better thanthat of fossil fired plants in the same size ranges, performanceduring construction has been variable. Although additional licensingrequirements, public intervention and funding problems have beenblamed for most of the delays and cost increases, there is growingrecognition that lack of proper project management has been a majorfactor.

Contents: Introduction; Project management — preparatory phase;Project management — execution phase; Appendix I: Sampleoutline of project manual; Appendix II: Manpower for utility projectmanagement; Appendix III. Manpower for main contractor projectmanagement; Appendix IV. Computerized treatment of projectschedules; Bibliography; Glossary.


Nuclear Power Operations

CODE ON THE SAFETY OF NUCLEAR POWER PLANTS: OPERATIONSafety Series No. 50-C-O (Rev. 1)

This code is prepared for those responsible for operating and regu-lating stationary nuclear power plants. Its safety requirements andrecommendations cover surveillance, operational limits and condi-tions, commissioning, plant management and site personnel, operat-ing instructions and procedures, maintenance, testing, examinationand inspection, modifications, radiologial protection, effluent andwaste management, emergency arrangements, quality assurance,security, records and reports, and decommissioning.

Contents: Definitions; 1. Introduction; 2. Surveillance by theoperating organization and by the regulatory body; 3. Operationallimits and conditions; 4. Commissioning; 5. Structure of the operat-ing organization; 6. Plant management and operating personnel;7. Operating instructions and procedures; 8. Maintenance, testing,examination and inspection; 9. Core management and fuel handling;10. Modifications; 11. Radiation protection; 12. Effluent and wastemanagement; 13. Emergency preparedness; 14. Quality assuranceprogramme; 15. Security; 16. Review of operation and feedback ofexperience; 17. Records and reports; 18. Decommissioning.

STI/PUB/799 (42 pp., 1 figure; 1988)E ISBN 92–0–123588–7C ISBN 92–0–523390–0F ISBN 92–0–223489–2R ISBN 92–0–423790–2S ISBN 92–0–323489–6Price: 160 Austrian schillings (€11.63)

COMMISSIONING PROCEDURES FOR NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-O4

This guide deals with the commissioning of all types of nuclearpower plants with thermal neutron reactors. Its purpose is to giveguidance on good practice, the implementation of which will enablecommissioning to proceed safely and provide assurances that theplant has been constructed and can operate according to designintent. The guide covers the programme of tests to be prepared andthe responsibility for implementing and reporting on the variousparts of the commissioning programme.

Contents: Introduction; Commissioning programme; Principalstages of commissioning; Testing procedures; Organization, respon-sibilities and audit; Interfaces between construction, commissioningand operating activities at the site; Deviations during commission-ing; Documentation; Appendix A: Fuel loading; Annex I: Detailedlist of commissioning tests; Definitions.

STI/PUB/574 (58 pp.; 1980)E out of printC ISBN 92–0–523187–8F ISBN 92–0–223981–9R ISBN 92–0–323881–6S ISBN 92–0–423282–XPrice: 180 Austrian schillings (€13.08)

DATA COLLECTION AND RECORD KEEPING FOR THE MANAGEMENT OF NUCLEAR POWER PLANT AGEINGSafety Series No. 50-P-3

This publication provides guidance on data requirements and aneffective and practical system for data collection and record keeping


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in relation to the evaluation and management of ageing and servicelife of nuclear power plant components. The application of the guid-ance will contribute to the safe and reliable operation of nuclearpower plants and will facilitate international information exchangeon ageing related component failures, malfunctions and degradation,since data collected using the same ground rules are easier toexchange and compare.

Contents: 1. Introduction; 2. General data needs for the evaluationand management of ageing; 3. Attributes of an effective data collec-tion and record keeping system; 4. General recommendations forimplementing the proposed data collection and record keepingsystem; Appendix I: Component specific data needs; Appendix II:Examples of effective data collection and record keeping systems;Appendix III: Guidance for implementation of an advanced datacollection and record keeping system; References; Glossary.


DEVELOPMENT AND IMPLEMENTATION OF COMPUTERIZED OPERATOR SUPPORT SYSTEMS IN NUCLEAR INSTALLATIONSTechnical Reports Series No. 372

(See under Reactor Technology, p. 88)

FEEDBACK OF OPERATIONAL SAFETY EXPERIENCE FROMNUCLEAR POWER PLANTSProceedings Series

Proceedings of a symposium jointly organized with OECD/NEA,Paris, 16–20 May 1988. Operating experience feedbackprogrammes have been extensively developed at various levelswithin the nuclear community and their effectiveness also hasimproved greatly as a result of: (a) the setting of more ambitiousplant targets providing greater margins in accident situations;(b) access to predictive operating data, indicative of the futureperformance of plants; and (c) the careful assessment, or review, ofpast operating experience to promptly correct the root causes of anyadverse trends. The purpose of the symposium was to provide aforum for the detailed exchange of experience for the discussion ofvarious ways of closing the feedback loop, with the ultimate goal ofenhancing the level of operational safety at nuclear power plants.

Contents: Opening session; Methods of identification of opera-tional safety issues in nuclear power plants; Methods of analysis ofoperational safety issues; Corrective actions implemented as a resultof operating experience; Operational safety experience feedbacksystems; Panel discussion: Operational safety of nuclear powerplants — future trends; Closing session.


IN-SERVICE INSPECTION FOR NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-O2

This guide outlines provisions for the preparation of in-serviceinspection programmes for critical systems and components ofprimary reactor coolant systems. Recommendations cover methodsand techniques applicable to in-service inspection and the minimumfrequency of examinations and tests. Methods of evaluating theresults are described and acceptance standards defined. Methods ofpreparing the necessary documentation, procedures and records arerecommended.

Contents: Introduction; Design considerations; In-service exam-ination; Evaluation of examination results; Test requirements;Repair and replacement; Equipment, methods and techniques;Administrative aspects; Records; Annex I: In-service inspection oflight-water-cooled reactor plants; Annex II: In-service inspection ofheavy-water-cooled pressure-tube reactor plants; Annex III: In-service inspection of gas-cooled reactor plants with pressure vessels.

STI/PUB/554 (47 pp.; 1980)E out of printC ISBN 92–0–523387–0F ISBN 92–0–223880–4R out of printS ISBN 92–0–823081–3Price: 160 Austrian schillings (€11.63)

MAINTENANCE OF NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-O7 (Rev. 1)

The guide covers the organizational and procedural aspects of effec-tive maintenance for safe operation of nuclear power plants, but doesnot provide detailed technical advice on the maintenance of particu-lar items. It gives guidance on preventive and remedial measuresnecessary to ensure safety. Experience from OSART missions andfrom the use of the manual on maintenance of systems and compo-nents important to safety was used for the revision. The sections onthe maintenance programme, administrative control and modifica-tions have been revised and a new section on the feedback of expe-rience developed.

Contents: Definitions; Note on the interpretation of the text;1. Introduction; 2. Maintenance programme; 3. Organization andresponsibilities for maintenance; 4. Administrative controls 5. Main-tenance facilities; 6. Replacements and repairs; 7. Modifications;8. Stores; 9. Feedback of experience; 10. Records; Surveillance,review and audit programme; Annex: Administrative aspects ofmaintenance work.

STI/PUB/848 (53 pp.; 1990)E ISBN 92–0–123190–3C ISBN 92–0–523491–5F ISBN 92–0–200192–8R ISBN 92–0–400392–8S ISBN 92–0–323591–4Price: 240 Austrian schillings (€17.44)

MAN–MACHINE INTERFACE IN THE NUCLEAR INDUSTRYProceedings Series

Proceedings of a conference organized in co-operation with CECand OECD/NEA, Tokyo, 15–19 February 1988. The conferencedemonstrated that the development of computer technologiesoffered great potential in the design of future control rooms fornuclear power plants with enhanced information processingcapabilities.

Contents: Opening remarks; Review of status and outlook; Humanbehaviour in plant operation; Plant personnel training; Operatorsupport; Artificial intelligence and accident management; Processcontrol and human engineering in control rooms; Robots for nuclearpower plant inspection and maintenance; Human engineering incontrols and control rooms; Transients and accident management;Robotics; Final panel; Closing remarks.


N U C L E A R P O W E R O P E R A T I O N S

86

MANAGEMENT OF NUCLEAR POWER PLANTS FOR SAFE OPERATION: A Safety GuideSafety Series No. 50-SG-O9

This guide identifies the main objectives and responsibilities ofmanagement with respect to the safe operation of nuclear powerplants. It discusses the factors to be considered in structuring theoperating organization to meet these objectives, in assigning theresponsibilities to units and individuals within the organization in anunambiguous manner, in establishing the management programmesfor ensuring that all safety requirements are met and in providing theservices and facilities needed for the accomplishment of these tasks.

Contents: Introduction; Management objectives and responsibili-ties; Structuring the operating organization; Managementprogrammes; Information and liaison; Supporting functions; Appen-dix A. Development of instructions and procedures; Appendix B.Development of operating and maintenance procedures.

STI/PUB/660 (56 pp., 3 figures; 1984)E ISBN 92–0–123984–XC ISBN 92–0–523791–4F ISBN 92–0–223984–3R ISBN 92–0–423386–9S ISBN 92–0–323085–8Price: 210 Austrian schillings (€15.26)

MANUAL ON MAINTENANCE OF SYSTEMS AND COMPONENTS IMPORTANT TO SAFETYTechnical Reports Series No. 268

This user’s manual provides Member States implementing the IAEACodes and Safety Guides (NUSS) with practical examples ofmanagement organization, good practices, methods and techniquesfor the maintenance of systems and components important to safety.It contains a detailed description of management systems, adminis-trative controls and procedures for maintenance activities and someaspects of surveillance and verification activities.

Contents: Introduction; Scope; Maintenance programme; Imple-mentation of maintenance programme; Surveillance and verificationactivities; Annex I. Examples of documents; Annex II. Descriptionsof practices.


OPERATING EXPERIENCE WITH ➜NEWNUCLEAR POWER STATIONS INMEMBER STATES IN 1998

This report is the thirtieth in the Agency’s series of annual reports onoperating experience with nuclear power stations in Member States.It is a direct output from the Agency’s Power Reactor InformationSystem (PRIS) and contains data on electricity production, overallplant operating performance and plant outage during 1998 for indi-vidual plants. In addition to annual performance data and outageinformation, the report contains a historical summary of perfor-mance and outages during the lifetime of individual plants andfigures illustrating worldwide performance and statistical data.

Contents: 1. Introduction; 2. Nuclear power station units inMember States; 3. Definitions; 4. Figures; 5. Abbreviations; 6. Datasheets on individual nuclear power station units.

STI/PUB/1087 (818 pp., 4 figures, 21 x 30 cm; 1999)ISBN 92–0–103199–8Price: 2350 Austrian Schillings (€170.78)

OPERATIONAL LIMITS AND CONDITIONS FOR NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-O3

The concept of operational limits and conditions for the safe opera-tion of nuclear power plants is presented. An essential element of theconcept is the distinction between safety limits established to retainthe integrity of fuel cladding and pressure boundary barriers, thesettings of safety systems provided to prevent safety limits frombeing exceeded or to initiate operation of engineered safety systems,and limits and conditions for normal operation established toprovide acceptable margins for operation.

Contents: 1. Introduction; 2. Concept of operational limits andconditions; 3. Contents of operational limits and conditions;4. Responsibilities of the operating organization; 5. Documentation.

STI/PUB/531 (35 pp.; 1979)E out of printC ISBN 92–0–524286–1F ISBN 92–0–223879–0R out of printS ISBN 92–0–323082–3Price: 140 Austrian schillings (€10.17)

SAFETY ISSUES FOR ADVANCED ➜NEWPROTECTION, CONTROL AND HUMAN–MACHINE INTERFACE SYSTEMS IN OPERATING NUCLEAR POWER PLANTSSafety Reports Series No. 6

This Safety Report identifies and describes safety and licensingissues reflecting international experience and practices and offersgood practices and effective safety approaches to digital instrumen-tation and control (I&C) retrofits in operating nuclear power plants.It provides valuable guidance to all those involved in upgradingprotection, control and human–machine interface systems in nuclearpower plants.

Contents: 1. Introduction; 2. Safety categorization and standards;3. Safety issues of advanced systems; 4. Methodologies to addresssafety issues; 5. Safety approaches for the human–machine inter-face; 6. Safety aspects of the upgrade process for advanced protec-tion, control and human–machine interface systems; Glossary.


Reactor Technology

ADVANCED NUCLEAR POWER SYSTEMS: DESIGN, TECHNOLOGY, SAFETY AND STRATEGIES FOR THEIR DEVELOPMENTProceedings Series

(See under Nuclear Power Planning and Economics, p. 82)

ANALYSIS OF THE BEHAVIOUR OF ADVANCED REACTOR PRESSURE VESSEL STEELS UNDER NEUTRON IRRADIATIONTechnical Report Series No. 265

The final report of an IAEA co-ordinated research programmeinvolving nine organizations in eight Member States during the


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period 1977–1983. The irradiation response of seven steels typicalof modern practice, in the form of plants, forgings and submergedarc welds supplied by worldwide suppliers, was determined underlight water reactor pressure vessel irradiation conditions.

Contents: Introduction; Scientific scope and programme goals;Standard part of Phase 2 programme; Irradiation conditions;Experimental results; Discussion of results; Conclusions; Appen-dix A: List of participants in the programme; Appendix B: Materi-als specification and identification; Appendix C: Expressions usedto define errors in linear regression analyses; Appendix D:Summary of experimental data; References; List of symbols andabbreviations.


BALANCING AUTOMATION AND HUMAN ACTION IN NUCLEAR POWER PLANTSProceedings Series

Proceedings of a symposium jointly organized with OECD/NEA,Munich, Germany, 9–13 July 1990. The purpose was to reviewdevelopments and to discuss directions for future efforts. Oneimportant aspect of nuclear safety in recent years has been the veryhigh rate of development and subsequent introduction of computertechnology. The data acquired by computer systems have to bepresented to the operator in a structured form with prioritizationcapabilities. Further developments of operator support systems mayconsiderably influence the interface between human control andautomation. To deal with fast transients, automation and real timesimulation have to be used. For other abnormal and accident situa-tions, human flexibility may be preferred. Full use must be made ofall plant resources, with system state and success path monitoringbeing of special interest in accident situations. The symposiumdiscussed all aspects of balancing problems, operating, maintenanceand testing, including all levels from information processing to fullautomation.

Contents: Opening session; Invited papers; Conceptions andachievements in automation; Safety implication of automation;Computerized operator support — Part I; Computerized operatorsupport — Part II; Man–machine interaction; Human factorsconsideration in automation; Accident management in automation;Future trends and needs (Panel discussion).


CODE ON THE SAFETY OF NUCLEAR POWER PLANTS: DESIGNSafety Series No. 50-C-D (Rev. 1)

This code establishes the general safety approach in design, sets outthe basic requirements to ensure the necessary system reliability anddefines the mandatory safety features of a nuclear power plant utiliz-ing thermal neutron reactors. The basic nuclear safety requirementsfor structures, systems and components compiled in this code areenlarged in the associated safety guides.

Contents: Definitions; 1. Introduction; 2. Safety philosophy;3. General design criteria; 4. Reactor core; 5. Reactor coolantsystem; 6. Information and control facilities; 7. Protection system;8. Emergency power supply; 9. Containment system; 10. Radiation

protection; 11. Fuel handling and storage systems; 12. Designconfirmation; Appendix: Postulated Initiating Events (PlEs).

STI/PUB/798 (58 pp., 1 figure; 1988)E ISBN 92–0–123488–0C ISBN 92–0–523290–4F ISBN 92–0–223389–6R out of printS ISBN 92–0–323389–XPrice: 190 Austrian schillings (€13.81)

COOLANT TECHNOLOGY OF WATER COOLED REACTORS: An OverviewTechnical Reports Series No. 347

This report is a survey of coolant technology in water cooled reac-tors which focuses on the following objectives: (a) man-sievertreduction; (b) plant life extension; (c) fuel life extension; (d) generalsafety and materials reliability.

Contents: 1. Introduction; 2. Description of reactor coolantsystems; 3. Chemistry of primary coolant in water cooled reactors;4. Corrosion in the primary coolant systems of water cooled reac-tors; 5. Activity transport mechanisms of water cooled reactors;6. Decontamination of water cooled reactors; 7. Areas for futureresearch and development; 8. Conclusions.


DECONTAMINATION OF WATER COOLED REACTORSTechnical Reports Series No. 365

This publication is the first comprehensive review of decontamina-tion processes used throughout the world on water cooled reactors,i.e. PWRs, BWRs, HWRs and WWERs, operating under reduceddose while under maintenance and repair. It focuses on the follow-ing objectives: man-sievert reduction, plant life extension, fuel lifeextension, and general safety and materials reliability. In addition,special attention has been given to full system decontaminationwhich is being developed in response to reactor ageing. Technicalissues such as materials compabitility, waste generation or reconta-mination after decontamination are also addressed.

Contents: 1. Introduction; 2. Nature of oxides and contamination;3. Physical, mechanical and electrochemical decontaminationprocesses; 4. Chemical decontamination processes; 5. Review ofexperience; 6. Technical issues.


DESIGN FOR REACTOR CORE SAFETY IN NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-D14

This guide covers the mechanical, chemical, thermal, hydraulic,neutronic and irradiation considerations important to the safe designof a nuclear reactor core. The core features of commonly usedreactor types including light and heavy water reactors, as well as gascooled reactors, are addressed.

Contents: Introduction; Safety design principles; Core designrequirements; Qualification and testing; Quality assurance in design,manufacture and operation; Annex 1. Reactivity coefficients;

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Annex II. Pellet–cladding interaction; Annex III. Design considera-tions for core management; Annex IV. Examples of postulated initi-ating events which can influence the core design.


DESIGN MEASURES TO FACILITATE ➜NEWIMPLEMENTATION OF SAFEGUARDS AT FUTURE WATER COOLED NUCLEAR POWER PLANTS Technical Reports Series No. 392

This report presents guidelines to the designers of water cooledpower reactors which will minimize the impact of IAEA safeguardson plant operations and ensure efficient and effective acquisition ofsafeguards data to the mutual benefit of the Member State, the plantoperator and the IAEA. These guidelines incorporate the IAEA’sexperience in establishing and carrying out safeguards at currentlyoperating nuclear power plants, the ongoing development of safe-guards techniques and the feedback of experience from plant opera-tors and designers on the impact of IAEA safeguards on plant oper-ation.

Contents: 1. Introduction; 2. The IAEA’s safeguards function forcurrent and future nuclear power plants; 3. Summary of the politicaland legal foundations of the IAEA’s safeguards system; 4. The tech-nical objective of safeguards and the supply and use of requireddesign information; 5. Safeguards approaches for nuclear powerplants; 6. Design implications of experience in safeguarding nuclearpower plants; 7. Guidelines for design provisions for future watercooled reactors to facilitate the implementation of safeguards;Appendix I: Summary of information requested in the IAEA’sDesign Information Questionnaire; Appendix II: IAEA safeguardsinstrumentation commonly used for power reactors; Glossary.


DEVELOPMENT AND IMPLEMENTATION OF COMPUTERIZED OPERATOR SUPPORT SYSTEMS IN NUCLEAR INSTALLATIONSTechnical Reports Series No. 372

This report addresses the development and implementation ofcomputerized operator support systems (COSS) in nuclear installa-tions. It discusses the requirements of operators in informationmanagement and job performance in control room environments.The design methodology described presents good practiceapproaches derived from the experience gained and the lessonslearned during actual development of the COSS.

Contents: 1. Introduction; 2. Computerized operator supportsystems; 3. Operational requirements; 4. Design methodology;5. Verification and validation; 6. Implementation; 7. Licensingconsiderations; Appendix I: Classification scheme for man–machineactivities; Appendix II: Techniques.


FAST BREEDER REACTORS: EXPERIENCE AND TRENDSProceedings Series

Proceedings of a symposium, Lyons, France, 22–26 July 1985. Thepurpose was to review experience gained in the field of LMFBRs,taking into account the constructional, operational, technological,economic and fuel cycle aspects, and to consider developmentaltrends and international co-operation in fast breeder reactor designand utilization.

Contents: (Vol. 1) Experience of LMFBR construction andoperation and resultant development strategies; LMFBR plantstartup and commissioning tests and general behaviour; Core perfor-mance experience for high burnup and core design trends; Experi-ence and trends in the LMFBR fuel cycle; Core design and behav-iour; Fuel and materials. (Vol. 2) Component design, performance,maintenance and repair; LMFBR plant design options and trends forgeneral layout; LMFBR components and plant design trends.

STI/PUB/697 (Vol. 1: 487 pp., 168 figures; Vol. 2: 657 pp., 301 figures;1986)1: ISBN 92–0–050086–22: ISBN 92–0–050186–9Price: Vol. 1: 1200 Austrian schillings (€87.21)


FLOW INDUCED VIBRATIONS IN LIQUID METAL FAST BREEDER REACTORSTechnical Reports Series No. 297

In the nuclear industry, flow induced vibrations are assessed early inthe design process and the results are incorporated in the designprocedures. This report is a general survey of experimental andcalculational methods in this area of structural mechanics. It waswritten by Dr. R.J. Gibert of CEA, France.

Contents: 1. Introduction; 2. Scope; 3. Fluidelastic phenomena:General description; 4. Methods used for the prediction of LMFBRvibrations; 5. Impact on the design; 6. Measurement and vibrationalmonitoring; 7. Conclusions and recommendations; References.


GAS COOLED REACTOR DESIGN AND SAFETYTechnical Reports Series No. 312

An update of Technical Reports Series No. 235, Status of andProspects for Gas Cooled Reactors, published in 1984; acompilation of information based on submissions from MemberStates describing the status of gas cooled reactors with specificemphasis on the design and safety characteristics of the variousconcepts that are either operating or are being designed and consid-ered for future construction and operation.

Contents: Chapter 1. Introduction; Chapter 2. Status of interna-tional gas cooled reactor development; Chapter 3. General featuresof gas cooled reactors and their safety characteristics; Chapter 4.Gas cooled reactor design and safety in the United Kingdom;Chapter 5. Gas cooled reactor design and safety in the United Statesof America; Chapter 6. Gas cooled reactor design and safety inJapan; Chapter 7. Gas cooled reactor design and safety in the Unionof Soviet Socialist Republics; Chapter 8. Gas cooled reactor designand safety in Switzerland; Chapter 9. Gas cooled reactor design andsafety in the Federal Republic of Germany; Chapter 10. Summary;Annex: Information exchange on gas cooled reactors.


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IMPLEMENTATION AND REVIEW OF ➜NEWA NUCLEAR POWER PLANT AGEING MANAGEMENT PROGRAMMESafety Reports Series No. 15

This publication provides information on good practices relating tothe implementation and review of an ageing managementprogramme (AMP) for nuclear power plants. AMPs are umbrellatype, systematic programmes integrating plant operations, inspec-tion and maintenance and other relevant programmes.

Contents: 1. Introduction; 2. Rationale for an AMP; 3. Descriptionof an AMP; 4. The AMP model and its implementation; 5. Reviewof an AMP; Appendix I: Data collection and record keeping; Appen-dix II: Examples of unanticipated ageing phenomena addressed byageing management teams; Appendix III: Indicators of AMP effec-tiveness.


MODERN INSTRUMENTATION AND CONTROL ➜NEWFOR NUCLEAR POWER PLANTSTechnical Reports Series No. 387

This report replaces Technical Reports Series No. 239, NuclearPower Plant Instrumentation and Control: A Guidebook (1984), inparticular by changing the emphasis from guidance to summarizingoperating experience and discussing new technologies. It providesan up to date overview of nuclear power plant instrumentation andcontrol technology and the background against which such systemsare implemented. It is directed to meet the needs of instrumentationand control engineers, but also of nuclear power plant designers andregulators.

Contents: 1. General introduction; Part I. Requirements, constraintsand recent issues; Part II. Design concepts; Part III. Recent develop-ments in instrumentation and control; Part IV. Instrumentation andcontrol in a new nuclear power plant; Part V. Examples of currentinstrumentation and control systems.


NUCLEAR DESALINATION OF SEA WATER ➜NEWProceedings Series

(See under Nuclear Power Planning and Economics, p. 84)

OFF-GAS AND AIR CLEANING SYSTEMS FOR ACCIDENT CONDITIONS IN NUCLEAR POWER PLANTSTechnical Reports Series No. 358

Air cleaning systems are subjected to major challenges under acci-dent conditions and the potential large source terms require thehighest environmental protection from atmospheric release. Theobjective of this report is to consider the principles involved and tosurvey existing systems and equipment for the mitigation of theconsequences of abnormal plant operations, including severe acci-dents beyond the design basis. Some experiences under abnormalconditions and international trends in the development of accidentair cleaning are also included.

Contents: 1. Introduction; 2. Source terms; 3. Design principles;4. Control of airborne contamination in design basis accidents;5. Control of airborne contamination in severe accidents; 6. Experi-ence and trends; 7. Conclusions and recommendations; Appendix:Testing of off-gas cleaning equipment for nuclear power plants.


REACTOR COOLANT AND ASSOCIATED SYSTEMS IN NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-D13

This guide covers the safety design considerations for variousreactor coolant and associated systems for operational states andaccident conditions including the selection, sizing and reliabilityaspects. This includes safety systems such as emergency corecooling, residual heat removal or emergency feedwater systems. Thedetailed design of particular components, e.g. heat exchangers,pumps and vessels, is not covered.

Contents: Introduction; Extent of the reactor coolant and associatedsystems; General design principles; Detailed design principles;Quality assurance; Annex I: Reactor coolant and associated systemsdiagrams; Annex II: Main reactor coolant system components;Annex III: Listing of pressure boundary codes and standards used insome Member States.

STI/PUB/731 (70 pp., 6 figures; 1986)E ISBN 92–0–123886–XF ISBN 92–0–223887–1R ISBN 92–0–423789–9S ISBN 92–0–323587–6Price: 260 Austrian schillings (€18.89)

SAFETY RELATED INSTRUMENTATION AND CONTROL SYSTEMS FOR NUCLEAR POWER PLANTS: A Safety Guide Safety Series No. 50-SG-D8

This guide deals primarily with design requirements for instrumen-tation and control systems that are important to safety, but are notpart of the protection system (Safety Series No. 50-SG-D3). It givesrecommendations on instrumentation and control systems for theprevention or termination of plant transients to avoid, if possible, theactuation of safety systems.

Contents: Introduction; Extent of the I&C systems; Design basis;Design requirements; Documentation; Appendix: Single failurecriterion for safety related I&C systems.

STI/PUB/678 (48 pp., 1 figure; 1984)E ISBN 92–0–623184–7F ISBN 92–0–223085–4R ISBN 92–0–423485–7S ISBN 92–0–323585–XPrice: 190 Austrian schillings (€13.81)

VERIFICATION AND VALIDATION OF ➜NEWSOFTWARE RELATED TO NUCLEAR POWER PLANT INSTRUMENTATION AND CONTROLTechnical Reports Series No. 384

This report provides practical guidance on the methods available forverification of the software and validation of computer basedsystems in nuclear power plants, and on how and when thesemethods can be effectively applied. It will be of particular interest toall those involved in the development, implementation, maintenance

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and use of software and computer based instrumentation and controlsystems in nuclear power plants.

Contents: 1. Introduction; 2. Safety classification and types of soft-ware; 3. Software related activities and documents; 4. Verificationby phase; 5. Validation; 6. Licensing; 7. Conclusions; Appendix I:Techniques for verification and validation; Appendix II: Singlefailure criterion; Appendix III: Experience.


Quality Assurance

IMPLEMENTATION OF QUALITY ASSURANCE CORRECTIVE ACTIONS: A ManualTechnical Reports Series No. 317

This manual was developed to serve as guidance on non-conformance and corrective actions which have been identified asthe major problems in the implementation of an effective qualityassurance programme. The scope of this manual, while fullyaddressing the requirements in the governing NUSS programmedocuments, also covers corrective action processes which wouldmore generally assist users in developing good practices forimproved performance in all areas of safety, reliability and econom-ics, and it offers a practical model and illustrative examples of themeans by which effective measures and actions can be implemented.

Contents: 1. Introduction; 2. Description of corrective actionprocess; 3. Identification of deficiencies; 4. Assessing and correctingdeficiencies; 5. Root cause analysis; 6. Verification and follow-up;7. Implementing procedures; 8. Trend analysis; 9. Summary; Defin-itions; References; Annex A: Example of a hold for QA clearancetag; Annex B: Examples of non-conformance report forms;Annex C: Example of a reject tag; Annex D: Example of a checklistfor reviewing non-conformance dispositions; Annex E: Examples ofa stop work notice and stop work notice tag; Annex F: Examples ofa deficiency report form and deficiency report–work order forms;Annex G: Example of a list defining a significant event for a nuclearpower plant; Annex H: Example of a method for evaluating person-nel caused deficiencies; Annex I: Example of a procedure for esca-lation to higher levels of management to achieve corrective action;Annex J: Example of a status report for corrective actions; Annex K:Example of a non-conformance control implementing procedure;Annex L: Example of a corrective action request implementingprocedure; Annex M: Example of an implementing procedure ontracking and trending of quality problems; Annex N: Example of amethod of coding of non-conformance data for defect analysis;Annex O: Example of reports available from a defect analysisprogramme.


MANAGEMENT FOR EXCELLENCE IN NUCLEAR POWER PLANT PERFORMANCE: A ManualTechnical Reports Series No. 369

The objective of this report is to facilitate a recognition of prioritymanagement issues which, when not adequately recognized andaddressed, can result in problems in operational performance atnuclear power plants. It provides a number of effective practices,reflecting the positive experience of nuclear power companies, that

have prevented or corrected problems related to selected manage-ment issues.

Contents: Executive summary; 1. Introduction; 2. Generic issuesrelated to effective management; 3. Effective practices; Annex 1:Designation of responsibility; Annex 2: Teamwork and effectivecommunication; Annex 3: Effectiveness of engineering activities;Annex 4: Surveillance of items important to safety and reliability;Annex 5. Peer evaluation; Annex 6. Working level self-assessment;Annex 7: Corrective action programme; Annex 8: Monitoring ofcorrective actions; Annex 9: Performance oriented quality depart-ment; Annex 10: Assessment overview group; Annex 11: Integratedperformance indicator system; Annex 12: Operating experiencefeedback; Annex 13: Self-assessment by the quality department;Annex 14: Focus on performance assessment; Annex 15: Qualitymaintenance teams; Annex 16: Performance enhancement stan-dards; Annex 17: Performance based quality training; Annex 18:Prioritization of work; Annex 19: Profit centre concept; Annex 20:Departmental meeting policy; Annex 21: Plant modification infor-mation system; Annex 22: Negotiated business plan; Annex 23:Improvement of personnel qualification; Annex 24: Computerizedmaintenance management system; Annex 25: Information manage-ment; Annex 26: Feedback to design; Annex 27: Definition of inter-faces; Annex 28: Teamwork and communication; Annex 29: Under-standing of management goals; Annex 30: Relationship with theregulator; Annex 31: Interface with the regulator; Annex 32:Personal performance appraisal; Annex 33: Business plan of thenuclear organization; Annex 34: Management development training;Annex 35: Supervisory development programme; Annex 36: Moni-toring of equipment condition; Annex 37: Career path programme.



Examples of typical QA functions to be undertaken and theassociated qualification requirements, training programmes, trainingtechniques and methods of certification of personnel implementingthese functions. Applicable to those participants in a nuclear powerproject who are associated with establishment and implementationof the various QA programmes during the life cycle of the project.

Contents: 1. Introduction; 2. QA programmatic and evaluationfunctions; 3. Inspection and test functions; 4. Training andqualification; 5. Maintenance of qualification; 6. Records; Annex I:Qualification; Annex II: Training; Annex III: National standards fortraining, qualification and certification; Annex IV: Examples ofpersonnel qualification record forms.



The revised Safety Code and its corresponding Safety Guidesreplace Safety Series No. 50-C-QA (Rev. 1), Code on the Safety ofNuclear Power Plants: Quality Assurance, and Safety Series Nos 50-SG-QA1 to 50-SG-QA11, and present new simplified basic require-ments and implementation methods for quality assurance in anuclear context. They provide recommendations to regulatory


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bodies in establishing regulatory requirements and in verifying theirimplementation, clearly formulate the responsibilities of the licenseein achieving improved quality and safety performance, and giveguidance on methods for fulfilling the basic requirements in amanner consistent with worldwide industry standards.

Contents: Glossary; Code; Safety Guides.

STI/PUB/1016 (364 pp., 6 figures; 1996)E ISBN 92–0–103696–5F ISBN 92–0–201998–3R ISBN 92–0–400898–9Price: 1040 Austrian schillings (€75.58)

QUALITY ASSURANCE INTEGRATED TRAINING PACKAGES: A ManualTechnical Reports Series No. 340

The competence of the personnel to establish and implement aneffective quality assurance programme is essential for attaining andmaintaining the safety, reliability and economic performance of anuclear installation. This manual offers training packages coveringquality assurance principles and practices which can be adjusted tosuit different levels of management and working personnel and canbe adapted to national variables and differing needs in the field ofquality assurance.

Contents: 1. Introduction; 2. General description; 3. Programmes ofclassroom training; 4. Lecture syllabuses for classroom training;5. On the job training; Appendix I: Typical training for inspection andtest personnel performing non-destructive examination; Appendix II:Typical training on the operating principles of an LWR power plant.


QUALITY MANAGEMENT FORNUCLEAR POWER PLANT OPERATION: A ManualTechnical Reports Series No. 315

This manual has been developed to assist plant managers infulfilling their responsibility with regard to the control and directionof quality and quality assurance activities in nuclear power plantoperation. It emphasizes quality objectives for nuclear power plantoperations and gives highlighted practices complemented by typicalexamples of forms and procedures. The selected activities comprisethose where it was felt that practical advice is generally needed.

Contents: 1. Introduction; 2. Quality management; 3. Competenceof personnel; 4. Operations; 5. Maintenance; 6. Deficiencies andcorrective actions; 7. Technical support; 8. Radiological safety;9. Emergency preparedness; 10. Feedback; Appendix A: Summaryof plant superintendent’s involvement and reviews listed in themanual; Appendix B: Typical organization of nuclear power plantoperations, showing the functions allocated to superintendents andmanagers; Annexes I–XXI.


REGULATORY INSPECTION OF THE IMPLEMENTATION OF QUALITY ASSURANCE PROGRAMMES: A ManualTechnical Reports Series No. 296

Guidance in the organization and performance of regulatory inspec-tion functions regarding the implementation of quality assurance

programmes in all stages of the nuclear power plant project. Themanual is intended primarily for the management personnel andupper staff from regulatory bodies but it will also be helpful tomanagement personnel from nuclear utilities and vendors.

Contents: 1. Introduction; 2. Techniques and methods of inspection;3. Performance of regulatory inspections of quality assuranceprogrammes; 4. Inspection reports; 5. Periodic evaluation of effec-tiveness of and trends in quality assurance programme performance;6. Enforcement of compliance with the quality assuranceprogramme; 7. Manpower requirements and technical qualificationsof quality assurance regulatory inspectors; Appendix I: Inspectionprocedure on document control; Appendix II: Inspection procedureon procurement control; Appendix III: Inspection procedure onreceipt, storage and handling of materials and equipment; AppendixIV: Inspection procedure on control of measuring and test equip-ment; Appendix V: Inspection procedure on non-conformancecontrol; Appendix VI: Inspection procedure on corrective action;Appendix VII: Inspection procedure on record system;Appendix VIII: Inspection procedure on auditing; Annex I: Exampleof inspection report cover page for licensee inspection; Annex II:Example of inspection report cover page for vendor inspection;Annex III: Example of legal framework for enforcement measures;Annex IV: Example of severity level categorization for enforcementpurposes; Annex V: Example of a system of civil penalties forenforcement purposes.


Qualification and Training of Personnel

ENGINEERING AND SCIENCE EDUCATION FOR NUCLEAR POWER: A GuidebookTechnical Reports Series No. 266

The guidebook provides recommendations, based on the experienceof both developed and developing countries, for upgrading or estab-lishing national education and training capabilities in engineeringand science in order to develop qualified personnel for nuclearpower programmes. Special consideration has been given to thespecific needs and conditions of developing countries.

Contents: Introduction; 1. Important aspects of engineering andscience education for nuclear power; 2. Nuclear orientedprogrammes in mechanical, electrical, chemical, nuclear, electronicsengineering and in radiation health physics; 3. Nuclear specializa-tion (S) programmes; 4. Undergraduate (U) and postgraduate (P)programmes in nuclear oriented mechanical (U1, P1), electrical (U2,P2) and chemical (U3, P3) engineering and postgraduateprogramme in nuclear engineering (P4) for graduates of nuclearoriented mechanical and electrical undergraduate programmes; 5.Integrated undergraduate (U) and post-graduate (P) programmes innuclear engineering (U5, P5) and radiation health physics (U6, P6);6. Basic nuclear science and engineering laboratory; 7. Measures forimplementing and improving engineering and science education andtraining capabilities for nuclear power personnel.


Q U A L I T Y A S S U R A N C E — Q U A L I F I C A T I O N A N D T R A I N I N G O F P E R S O N N E L

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GUIDEBOOK ON THE EDUCATION AND TRAINING OF TECHNICIANS FOR NUCLEAR POWERTechnical Reports Series No. 306

This guidebook describes for nuclear technicians: (1) the necessarylevel and content of conventional education and training; (2) thelevel and content of nuclear oriented education and training; (3)measures to bridge the gap between the two. The guidebook comple-ments or is supplemented by Technical Reports Series No. 200,Manpower Development for Nuclear Power; Technical ReportsSeries No. 242, Qualification of Nuclear Power Plant OperationsPersonnel; and IAEA-TECDOC-526, Appendices to the Guidebookon the Education and Training of Technicians for Nuclear Power.This guidebook seeks to assist policy makers and planners, as wellas those designing and implementing education and trainingprogrammes.

Contents: Introduction; 1. Definition of technicians; 2. Planningand implementation of the E&T of technicians for nuclear power;3. Recommended E&T requirements to enter nuclear oriented E&T;4. Upgrading the E&T of technicans who will enter nuclear orientedE&T; 5. Education and training of teachers/trainers for a nuclearpower programme; 6. Functions, tasks and number of technicians ina nuclear power programme; 7. Basic and specialized E&T for anuclear power programme; 8. Nuclear science and engineering labo-ratory; 9. Mechanisms for education and training implementation.



(See under Quality Assurance, p. 90)

NUCLEAR POWER PLANT PERSONNEL ➜NEWTRAINING AND ITS EVALUATION: A GuidebookTechnical Reports Series No. 380

This guidebook is a revision and update of the IAEA Guidebook onTraining to Establish and Maintain the Qualification and Compe-tence of Nuclear Power Plant Operations Personnel, IAEA-TECDOC-525, published in 1989. It incorporates the experiencegained since the introduction of the Systematic Approach to Train-ing (SAT) for nuclear power plant personnel six years ago andemphasizes a broader concept of competence which includes notonly technical knowledge and skills but also knowledge, skills andattitudes related to human factors. In addition to the training of oper-ating personnel, the Guidebook deals with the role and responsibil-ities of management; the training of management and maintenancepersonnel; organizations involved in training; and more effectiveand efficient methods of SAT analysis.

Contents: 1. Introduction; 2. The role of management; 3. The roleof training organizations and the organization of training; 4. SATmethodology overview; 5. Analysis; 6. Design; 7. Development;8. Implementation; 9. Evaluation; 10. SAT applications; 11. IAEAactivities and technical co-operation in NPP personnel training andqualification.


QUALITY ASSURANCE INTEGRATED TRAINING PACKAGES: A ManualTechnical Reports Series No. 340

(See under Quality Assurance, p. 90)

STAFFING OF NUCLEAR POWER PLANTS AND THE RECRUITMENT, TRAINING AND AUTHORIZATION OF OPERATING PERSONNEL: A Safety GuideSafety Series No. 50-SG-O1 (Rev. 1)

This guide outlines the factors to be considered to ensure that theoperating organization has a sufficient number of qualified sitepersonnel who are aware of their duties and responsibilities. Itcovers the organization for the nuclear power plant, the educationalqualifications and experience of the persons recruited, the recruit-ment and training schedule, the training of operating personnel, theauthorization of persons whose duties have an immediate bearing onsafety, and re-training of personnel.

Contents: Definitions; 1. Introduction; 2. Organizational plan;3. Recruitment; 4. Training and qualification; 5. Authorization;6. Records; Annex: Nuclear power plant organizational charts.

STI/PUB/874 (59 pp., 5 figures; 1991)E ISBN 92–0–123391–4F ISBN 92–0–203195–1 R ISBN 92–0–405095–0S ISBN 92–0–302095–0Price: 240 Austrian schillings (€17.44)


NUCLEAR FUEL CYCLE ANDWAS TE MANAGEMENT

NUCLEAR COMMUNICATIONS: A HANDBOOK FOR GUIDING GOOD COMMUNICATIONS PRACTICES AT NUCLEAR FUEL CYCLE FACILITIES

The purpose of this handbook is to serve as a guideline in applying good communications practices concerning nuclear fuelcycle facilities. It provides a compact source of information forpeople involved in plant operation and management and identifiesand addresses questions that members of the public may have aboutdifferent aspects of the nuclear fuel cycle.

Contents: 1. Introduction; 2. Energy, society and the environment;3. The nuclear fuel cycle and the environment; 4. Specific issues,questions and responses; Appendices: I. Uranium exploration andmining: Examples of codes of conduct and practices; II. Organizingcommunication for a new facility: A case study; III. Consultants andadvisory group members.


NUCLEAR FUEL CYCLE AND REACTOR ➜NEWSTRATEGIES: ADJUSTING TO NEW REALITIESProceedings Series

Key issue papers from a symposium held in co-operation with theEC, the OEC/NEA and the Uranium Institute, 3–6 June 1997,Vienna. The purpose of the symposium was to provide a forum fordiscussion of the new realities facing the nuclear fuel cycle and toconsider options on how these could be addressed. Amongst the newrealities are the facts that: nuclear capacities have increased less thanprojected; the debate on the choice of the most appropriate fuelcycle is still ongoing; military stocks of weapon plutonium andhighly enriched uranium have been released; and the amount ofplutonium in the world is continuously increasing. The datacontained in these key issue papers should assist to inform decisionmakers and the public and lead to a more objective discussion of thedifferent options in the nuclear fuel cycle.

Contents: Key issue paper No. 1: Global energy outlook; Key issuepaper No. 2: Present status and immediate prospects of plutoniummanagement; Key issue paper No. 3: Future fuel cycle and reactorstrategies; Key issue paper No. 4: Safety, health and environmentalimplications of the different fuel cycles; Key issue paper No. 5:Non-proliferation and safeguards aspects; Key issue paper No. 6:International co-operation.


NUCLEAR FUEL CYCLE IN THE 1990s AND BEYOND THE CENTURY: SOME TRENDS AND FORESEEABLE PROBLEMSTechnical Reports Series No. 305

This publication contains comprehensive analyses of selected stagesof the nuclear fuel cycle with an outlook to the near future and withemphasis on the advantages as well as the disadvantages of theapproaches discussed. Its aim is to highlight selected subjects ofinternational interest and establish a starting point for productivediscussions on the future of the nuclear fuel cycle worldwide.

Contents: Trends in the nuclear fuel cycle: Development in the1990s and international co-operation; Uranium supply and demand:Are there reasons for anxiety? AVLIS technology: Principal advan-tages and problems; Use of MOX fuels: The reasons to start; Fabri-cation, characterization and quality control of nuclear fuel ceramics.


SAFE HANDLING AND STORAGE ➜NEWOF PLUTONIUMSafety Reports Series No. 9

This Safety Report updates IAEA Safety Series No. 39, SafeHandling of Plutonium (1974), and provides an overview of modernpractices for handling and storing separated plutonium. It providesdescriptions of plutonium and its properties, and of the biologicaleffects on humans of plutonium. The principles underlying the safedesign and operation of plutonium handling/storage facilities andthe licensing of such facilities are also covered.

Contents: 1. Introduction; 2. Current and future plutonium activitiesand inventories; 3. Nuclear, physical and chemical properties ofplutonium; 4. Plutonium in the environment; 5. Pathways to humansand the biological effects of plutonium; 6. Licensing, controls andregulatory limits; 7. Safety aspects of design; 8. Operational safety;9. Summary; Annex I. Examples of plutonium plant design; AnnexII. Radiological safety data for plutonium handling; Annex III. Crit-icality safety parameters; Glossary.


THE NUCLEAR FUEL CYCLE INFORMATION ➜NEWSYSTEM: A Directory of Nuclear Fuel Cycle Facilities — 1996 Edition

The Nuclear Fuel Cycle Information System (NFCIS) is an international directory of civilian nuclear fuel cycle facilities. Itspurpose is to provide information on existing and planned

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commercial nuclear fuel cycle facilities, including some pilot andlaboratory scale facilities (altogether 433 facilities throughout theworld). The information contained in NFCIS, a computerized data-base, is obtained through questionnaires from IAEA Member Statesor other authoritative published sources. The individual recordscontain information on the name and location of each facility,together with technical information such as process and nameplatecapacity, startup and shutdown dates. The addresses of the technicaloperator and of the major shareholder are usually also provided.

Contents: Introduction; The nuclear fuel cycle industry; Nuclearfuel cycle processes and facilities; Scope of the nuclear fuel cycleinformation system; The NFCIS database; Glossary; The NuclearFuel Cycle Directory.


Uranium Ore Processing

CURRENT PRACTICES FOR THE MANAGEMENT ANDCONFINEMENT OF URANIUM MILL TAILINGSTechnical Reports Series No. 335

The present report provides an updated and comprehensiveoverview of the subject and supersedes Technical Reports SeriesNo. 209, Current Practices and Options for Confinement of UraniumMill Tailings, published in 1981. The present worldwide productionof uranium mill tailings exceeds 20 million tonnes annually. lt istherefore essential that the environmental and health risks fromthese materials are reduced to an acceptable level. This report high-lights new technological developments in this field as well as oper-ational and managerial experience arising from the application ofthese methods.

Contents: 1. Introduction; 2. Scope; 3. Mining and milling uraniumores; 4. Factors in the management of uranium mill tailings;5. Release of pollutants from uranium mill tailings to the humanenvironment; 6. Environmental considerations in mill process selec-tion; 7. Impoundment siting and design options; 8. Treatment ofliquid effluents and monitoring; 9. Stabilization and rehabilitation ofimpoundments; 10. Application of radiological protection princi-ples; 11. Assessing the long term safety of closeout options;12. Summary and conclusions; References; Additional bibliograph-ical references; Appendix I: An example of the use of mathematicalmodels to assess the long term safety of mill tailings closeoutoptions; Appendix II: Abbreviated checklist of considerations rele-vant to the design, construction and closeout of uranium mill tailingsimpoundments; Glossary.


DECOMMISSIONING OF FACILITIES FOR MINING AND MILLING OF RADIOACTIVE ORES AND CLOSEOUT OF RESIDUESTechnical Reports Series No. 362

The purpose of this report is to provide an overview of the factorsinvolved and assistance in planning and implementing the decom-missioning of mining and milling facilities and the closeout ofmines, tailings piles, mining debris and leach residues. Restorationof the site, vicinity properties and groundwater is also part of thereport.

Contents: 1. Introduction; 2. Purpose; 3. Scope; 4. Objectives ofdecommissioning/closeout programmes; 5. Regulatory control fordecommissioning/closeout; 6. Site characterization; 7. Planning andtechnical considerations; 8. Implementation of the decommission-ing/closeout plan; 9. Radiation protection, health and safetyprogrammes during decommissioning/closeout activities; 10. Post-closeout monitoring and surveillance programmes; 11. Cost esti-mating and financing for decommissioning/closeout; 12. Documen-tation for decommissioning/closeout; 13. QA programme fordecommissioning/closeout; 14. Summary and conclusions; Annex I:Examples of national regulatory requirements, regulations and crite-ria for mill tailings and the decommissioning/closeout of uraniummines/mills; Annex II: Examples of national criteria for the exemp-tion, release or cleanup of radioactive sites, buildings, equipmentand materials from the decommissioning/closeout of uraniummines/mills; Annex III: Geotechnical, hydrological, environmentaland economic rating matrix; Annex IV: Checklist for revegetation ofdecommissioned uranium tailings; Annex V: Longevityrequirements; Annex VI: National experience in the decommission-ing/closeout of facilities and residues from the mining and millingof radioactive ores.


DEVELOPMENT OF PROJECTS FOR THE PRODUCTION OF URANIUM CONCENTRATESPanel Proceedings Series

Proceedings of a meeting, Vienna, 25–28 November 1985. Themeeting was designed to bring together specialists from developedand developing countries to discuss the problems of planning andimplementing complete mining-metallurgical projects for uraniumand to review selected case histories in project development.

Contents: Development of projects for the production of uraniumconcentrates: An overview; International co-operation in radiationprotection practices in the mining and milling of uranium; A millingand conversion pilot plant at Ningyo Toge, Japan; Construction of anew plant in Gabon by the Compagnie des mines d’uranium deFranceville: Three years’ experience of operation; A new unit forpurification of uranium solution in the Lodève mill; Developmentstatus of projects for uranium production; The Key Lake project;Development of a system for the automation of a grinding circuit;Test procedures for the metallurgical evaluation of uranium ores;The uranium mill of the Compagnie minière Dong-Trieu: Projectpreparation and implementation; Development of uraniumoperations in Saskatchewan; Computer system for optimizing auranium extraction process; In-place leaching of uranium at DenisonMines Ltd; Techniques for heap and in situ leach simulation onuranium ores; The Chemwes uranium plant: A case history; Annex:National reports on the current status of uranium ore processing inCanada, Columbia, Mexico, the United States of America andYugoslavia.


GUIDEBOOK ON DESIGN, CONSTRUCTION and OPERATION OF PILOT PLANTS FOR URANIUM ORE PROCESSINGTechnical Reports Series No. 314

The design, construction and operation of a pilot plant are oftenimportant stages in the development of a project for the productionof uranium concentrates. The main purpose of this guidebook is to

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discuss the objectives of a pilot plant and its proper role in theoverall project. Since building and operating a pilot plant is verycostly, it is important that such a plant be built only after severalprerequisites have been met. This book discusses the rationale for apilot plant and provides guidelines with suggested solutions for avariety of problems that may be encountered.

Contents: 1. Introduction; 2. Process selection and design; 3. Basicengineering; 4. Project administration; Appendix I: Example of auranium pilot plant; Appendix II: General and radiological safety;Annex: Basic data; References; Bibliography.


MANUAL ON LABORATORY TESTING FOR URANIUM ORE PROCESSINGTechnical Reports Series No. 313

Laboratory testing of uranium ores is an essential step in theeconomic evaluation of uranium occurrences and in the develop-ment of a project for the production of uranium concentrates.Although these tests represent only a small proportion of the totalcost of a project, their proper planning, execution and interpretationare of crucial importance. This manual discusses the objectives ofmetallurgical laboratory ore testing, shows the specific role of thesetests in the development of a project and provides practical instruc-tions for performing the tests and for interpreting their results.Guidelines on the design of a metallurgical laboratory, on the equip-ment required to perform the tests and on laboratory safety are alsogiven.

Contents: 1. Introduction; 2. Sampling and characterization; 3. Sizereduction; 4. Leaching; 5. Solid–liquid separation and washing;6. Uranium recovery from leach solutions; 7. Uranium recovery byion exchange; 8. Uranium recovery by solvent extraction; 9. Precip-itation; 10. Alternative techniques; 11. Flow sheets and materialbalances; 12. Report writing; Appendix I: Laboratory safety; Appen-dix II: Guidelines for laboratory design; Appendix III: Suggestedlaboratory equipment and supplies.


MEASUREMENT AND CALCULATION OF RADON RELEASES FROM URANIUM MILL TAILINGSTechnical Reports Series No. 333

The present report provides a comprehensive overview of therelease, control and monitoring of radon. lt complements TechnicalReports Series No. 335, Current Practices for the Management andConfinement of Uranium Mill Tailings, which provides a generalaccount of the siting, design and construction of tailingsimpoundments.

Contents: Notation; 1. Introduction; 2. Purpose and scope;3. Factors controlling radon releases; 4. Methods for calculatingradon releases from uranium tailings piles; 5. Measurement of radonconcentration and flux; 6. Conducting a radon monitoringprogramme; 7. Summary; Annex A: Mathematical development ofradon diffusion equations; Annex B: Refined methods of radon fluxcalculation; References; Glossary.


URANIUM EXTRACTION TECHNOLOGYTechnical Reports Series No. 359

The purpose of this publication is to update and expand the firstedition, which was published in 1983, and to report on advances inuranium ore processing which have taken place since. It includesbackground information about the principles of the unit operationsused in uranium ore processing and summarizes the current state ofthe art. It also seeks to preserve the technology and the operating‘know-how’ developed over the past ten years. Extensive referencesprovide sources for specific technological details.

Contents: Introduction; Part I. Uranium resources and mining tech-nology; Chapter 1. Uranium resources; Chapter 2. Mining technol-ogy; Part II. Processing technology; Chapter 3. Processing concepts;Chapter 4. Ore preparation; Chapter 5. Leaching; Chapter 6.Solid–liquid separation; Chapter 7. Solution purification; Chapter 8.Product recovery; Chapter 9. By-products; Part III. Waste manage-ment and the environment; Chapter 10. Tailings management tech-nology; Part IV. Flow sheet examples; Chapter 11. Olympic Dam;Chapter 12. Key Lake; Chapter 13. Rabbit Lake; Chapter 14.Lodève; Chapter 15. Rossing; Chapter 16. Cominak; Chapter 17.White Mesa; Chapter 18. Rosita (in situ leaching).


Fuel Fabrication and Performance

DESIGN AND PERFORMANCE OF WWER FUEL ➜NEWTechnical Reports Series No. 379

This report is the first of its kind presenting compiled information onall aspects of fuel for pressurized water reactors (WWERs orVVERs) of the two sizes in use, WWER-440 and WWER-1000. Itcovers design principles, and detailed design and fabricationprocesses, as well as fuel performance under normal operation, highburnup effects, effects of load following, effects of reactivity inser-tion accidents, fuel defect experience and fuel performance model-ling. It is intended to serve as a comprehensive reference on thedesign and performance of WWER fuel.

Contents: 1. Introduction; 2. WWER fuel element design; 3. Fuelelement fabrication processes; 4. Fuel element performance innormal operation; 5. High burnup effects; 6. Effects of loadfollowing; 7. Effects of operational transients and loss of coolantaccidents (LOCAs); 8. Effects of reactivity insertion accidents;9. Fuel defect experience; 10. Fuel performance modelling;11. Future prospects; 12. Summary.


GUIDEBOOK ON DESTRUCTIVE ➜NEWEXAMINATION OF WATER REACTOR FUELTechnical Reports Series No. 385

This guidebook gives a complete survey of destructive techniquesavailable to perform microstructural examinations, elemental andisotopic analyses and measurement of physical, chemical andmechanical properties of irradiated fuel and structural materials, anddescribes asociated refabrication and instrumentation techniques.Non-destructive examination (NDE) data are verified by destructiveexamination (DE) data. The data were submitted to the IAEA by hotlaboratories from 12 countries and one international organization(CEC/ITU) during the period 1992–1995. Together with IAEA

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Technical Reports Series No.322 (1991), Guidebook on non-destructive examination of water reactor fuel, it presents the mostcomprehensive summary of post-irradiation examination techniquesto date.

Contents: 1. Introduction; 2. Microstructural studies; 3. Elementalanalysis; 4. Isotopic analysis; 5. Measurement of physicalproperties; 6. Measurement of mechanical properties; 7. Refabrica-tion and instrumentation; 8. Verification of non-destructive tech-niques by destructive methods; 9. Conclusions.


GUIDEBOOK ON NON-DESTRUCTIVE EXAMINATION OF WATER REACTOR FUELTechnical Reports Series No. 322

The guidebook gives a complete survey of non-destructive tech-niques available for application in the spent fuel pool as well as inhot cells, thereby supplementing an earlier publication, IAEA-TECDOC-245. It provides information on methods of examiningwater reactor fuel and a basis for further innovations.

Contents: 1. Introduction; 2. Defect surveillance and detection;3. Visual inspection; 4. Dimensional measurements; 5. Oxide layerthickness and crud measurements; 6. Gamma scanning; 7. Neutronradiography and X ray radiography; 8. Fission gas determination;9. Transfer, collection, documentation and storage of post-irradia-tion data; 10. Conclusions.


IMPROVEMENTS IN WATER REACTOR FUEL TECHNOLOGY AND UTILIZATIONProceedings Series

Proceedings of a symposium, Stockholm, 15–19 September 1986.The aim of the symposium was to exchange information on achieve-ments made and future work. It was shown that water reactor fuelsperform reliably and meet performance requirements. The factorswhich could limit performance under high burn-up conditions andload follow mode of operation were discussed and defined. Currentdevelopment is primarily related to studies of water-side corrosion,pellet–cladding interaction, fission gas release, dimensional stabil-ity, use of burnable absorbers, in-core fuel management and variousfabrication processes.

Contents: Introduction; Fuel design and performance; Fuelmaterials and behaviour; Structural materials; Fuel fabrication;Poster sesssion; Closing session.


REVIEW OF FUEL ELEMENT DEVELOPMENTS FOR WATER COOLED NUCLEAR POWER REACTORSTechnical Reports Series No. 299

Improvements in water reactor fuel technology and utilization areof great importance in achieving better reactor operational safetyand economics. This report is intended to provide general informa-tion on the progress made in water reactor fuel design, fabricationand utilization, as well as on current and future developments.

Contents: 1. Introduction; 2. The nuclear fuel cycle; 3. Fuel and fuelelement fabrication; 4. Quality control; 5. Fuel element design andperformance; 6. Major developments and water reactor fuel perfor-mance experience in selected countries; 7. Fuel management: Incen-tives to improve fuel utilization; 8. Conclusions.


REVIEW OF FUEL FAILURES IN ➜NEWWATER COOLED REACTORSTechnical Reports Series No. 388

The purpose of this report is to provide a combined presentation ofthe worldwide experience gained on fuel failures in water cooledreactors and to give statistical data on fuel failures for the period1987 to 1994. It contains detailed descriptions of primary andsecondary failure mechanisms which occurred in ‘western’ typeboiling and pressurized water reactors (BWRs and PWRs), Soviettype pressurized light water reactors (WWERs) and Canadian typeheavy water reactors (CANDUs). It also includes information ondetection, examination and analysis of fuel failures as well as on fuelfailure prevention and management in plant operation.

Contents: 1. Introduction; 2. Historical remarks on fuel failure anddesign evolution; 3. World overview on fuel failures in 1987–1994;4. Detection, examination and analysis of fuel failures; 5. Mecha-nisms and root causes of fuel failures; 6. Secondary fuel failures;7. Fuel failure prevention and management in plant operation;Conclusions and recommendations.


WATER REACTOR FUEL EXTENDED BURNUP STUDYTechnical Reports Series No. 343

This report details the results of the Water Reactor Fuel ExtendedBurnup Study (WREBUS), the first internationally conducted studyof its kind. The report assesses the economic effects of burnupextension, evaluates uranium utilization for PWRs and BWRs (e.g.the need for higher enrichments and possible fuel design changes)and considers environmental, safety and licensing implications. Theresults of the study provide a basis for understanding incentives andindicating directions for future developments in fuel cycle technolo-gies and for introducing improvements in fuel performance andoperational strategies.

Contents: 1. Introduction; 2. Incentives for extending burnup;3. Economic evaluation; 4. Technical aspects; 5. Conclusions;Appendix: Description of the fuel cycle cost method used for the UScontribution.


Spent Fuel Management

BACK END OF THE NUCLEAR FUEL CYCLE: STRATEGIES AND OPTIONSProceedings Series

Proceedings of a symposium jointly organized with OECD/NEA,Vienna, 11–15 May 1987. The symposium addressed a vital and


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common subject for all countries developing nuclear power, namelywhat to do with nuclear fuel after its discharge from the reactor. Itprovided a forum for the exchange of information on the analysisand selection of spent fuel management, national strategies andincentives for international co-operation, as well as on the varioustechnical, safety, economic, environmental, legal and regulatoryaspects associated with spent fuel and high level waste (HLW)management.

Contents: National approaches to the back end of the nuclear fuelcycle; Options and strategies for the back end of the nuclear fuelcycle; Transportation of spent fuel and radioactive waste; Handling,conditioning and storage of spent fuel and HLW; Developmentprogrammes for reprocessing facilities; Utilization of materialsrecovered by reprocessing; Disposal of spent fuel and HLW; Closingsession (Summary of Symposium).


CONCEPTS FOR THE CONDITIONING OF SPENT NUCLEAR FUEL FOR FINAL WASTE DISPOSALTechnical Reports Series No. 345

This report describes various national spent fuel conditioningconcepts, the current state of technology, the waste package designsso far developed, and the engineering operations required for theirmanufacture. It supplements IAEA Technical Reports SeriesNo. 320, Evaluation of Spent Fuel as a Final Waste Form.

Contents: 1. Introduction; 2. Major factors in the development ofconditioning concepts; 3. Waste package design; 4. Preconditioningprocesses; 5. Conditioning processes; 6. Summary; Appendix:National spent fuel conditioning concepts.


COST ANALYSIS METHODOLOGY OF SPENT FUEL STORAGETechnical Reports Series No. 361

This report provides a methodology for calculating the costs ofdifferent options for interim storage of spent fuel produced inreactor cores. It considers different technical features and storageoptions and defines the factors affecting all options. The reportfurther analyses the major cost categories, calculates the net presentvalue of each option and determines the levelized cost. It alsoincludes a sensitivity analysis, taking into account the uncertainty ofthe different cost estimates.

Contents: 1. Introduction; 2. Spent fuel management; 3. Technicalfeatures of spent fuel storage; 4. Storage options and cost consider-ations; 5. Cost considerations; 6. Method of cost analysis; 7. Costanalysis; 8. Financing the options; Appendix I: AR storage enhance-ment: Reracking with compact storage racks in Germany; Appen-dix II: A stand alone AR storage facility: The TVO-KPA poolstorage facility at Olkiluoto in Finland; Appendix III: An AFRstorage facility: The CLAB pool storage facility at Oskarshamn inSweden; Appendix IV: An AFR storage facility: Pool storagefacilites at the Cogéma processing plant at La Hague in France;Appendix V: An AFR storage facility: The dry cask storage facilityat Gorleben in Germany.


DESIGN OF SPENT FUEL STORAGE FACILITIES:A Safety StandardSafety Series No. 116

This guide has been developed through a series of technical meet-ings and represents an international consensus on useful design prin-ciples. These principles incorporate features which will be effectivein maintaining fuel subcritical, removing residual heat, providingradiation protection and containing radioactive materials for the life-time of the facility. It is intended for use by the nuclear power indus-try, its supporting organizations and related regulatory bodies inidentifying and managing all relevant issues on the design aspectsfor the safe interim storage of spent fuel from nuclear power plants.It complements Safety Series No. 117, Operation of Spent FuelStorage, and Safety Series No. 118, Safety Assessment for SpentFuel Storage Facilities.

Contents: 1. Introduction; 2. General guidance; 3. Specificdesign requirements; 4. Auxiliary systems; 5. Quality assur-ance; 6. Inspection and maintenance; 7. Decommissioning;Definitions.


EVALUATION OF SPENT FUEL AS A FINAL WASTE FORMTechnical Reports Series No. 320

The present report provides an appreciation of the types and quanti-ties of spent fuel for disposal and reviews the current state of knowl-edge of the behaviour of spent fuel under repository conditions. Itfurther contains comments and discussions on technical and safetyaspects specific to the disposal of spent fuel, discussed at a Techni-cal Committee meeting held in Vienna in June 1988.

Contents: 1. Introduction; 2. Type of spent fuel; 3. Effect ofin-reactor operations on fuels; 4. Behaviour of spent fuel in thedisposal environment; 5. Safety and environmental assessments ofspent fuel as a final waste form; 6. Engineering evaluations anddemonstrations of spent fuel disposal; 7. Summary.


FEASIBILITY OF SEPARATION AND UTILIZATION OF CAESIUM AND STRONTIUM FROM HIGH LEVEL LIQUID WASTETechnical Reports Series No. 356

(See under Waste Management, p. 103)


Proceedings of a symposium organized jointly with CEC andOECD/NEA, Antwerp, Belgium, 19–23 October 1992. The purposeof the symposium was to review the progress being made in nationaland international programmes towards the demonstration of safedisposal of radioactive wastes. The technical presentationsaddressed disposal in all the principal geological media currentlyunder consideration: clay, crystalline rock, salt and volcanic tuff.The programmes described ranged from national screening surveyson a broad, regional scale to detailed site specific investigations inunderground research laboratories.

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Contents: Keynote address; Programmes of internationalorganizations; Site characterization programmes and methods;Repository design concepts, construction techniques and engineeredbarrier design; Characterization and acceptance of high level andalpha bearing wastes; Repository concepts for direct disposal ofspent fuel; Developing, testing and validating repository perfor-mance assessment models; National and international programmes;Poster presentations.


GUIDEBOOK ON SPENT FUEL STORAGE — Second Edition Technical Reports Series No. 240/2

This guidebook is a revised version of Technical Reports SeriesNo. 240, published in 1984. It provides a summary of the experienceand information in many areas related to spent fuel storage. It willallow a better understanding of the many problems involved andpermit countries that are planning for or operating nuclear powerreactors to review the issues in a more informative manner. In viewof the large quantity of spent fuel discharged from nuclear powerplants, long term storage is currently the primary option for themanagement of spent fuel. The proven wet storage concept isexpected to continue to be used in the future. The design and thetechnological, economic and material problems of safe spent fuelstorage will remain a focus of attention, with particular emphasis ondry storage technology, rod consolidation and other advancedconcepts.

Contents: 1. Introduction; 2. Spent fuel storage technology;3. Transport of spent fuel; 4. Economics of spent fuel storage;5. Regulatory, institutional and safety aspects; 6. International safe-guards; 7. Factors used in evaluating spent fuel storage options;8. International co-operation; Annex A: AFR storage facility Clab,Sweden; Annex B: Development of AFR storage design in theUSSR; Annex C: Spent fuel storage in the Federal Republic ofGermany; Annex D: United States horizontal concrete dry storagesystem; Annex E: Canadian experience with the dry storage of usedCANDU fuel; Annex F: United States dry cask storage experience;Annex G: United States experience with spent fuel rod consolida-tion; Annex H: Fuel storage ponds at Sellafield, United Kingdom;Annex I: Acronyms and abbreviations; Annex J: Glossary.

STI/DOC/10/240/2 (207 pp., 71 figures; 1991)ISBN 92–0–155191–6Price: 620 Austrian schillings (€45.06)


This report provides a comprehensive review of managementinsights and principles for the on-site, post-accident activities atnuclear power plants that have experienced significant fuel damage.Member States who wish to complement their emergency responseprocedures and off-site plans with knowledge of on-site experiencewill find this publication useful for such a purpose. It will alsoprovide a reference text on the requirements that arise after the crit-ical phase of emergency response.

Contents: 1. Introduction; 2. Strategic planning; 3. Stabilizing thefuel; 4. Data management and analysis; 5. Initial waste manage-ment; 6. Initial decontamination; 7. Fuel removal; 8. Fuel condi-tioning, transport and interim storage; 9. Abnormal waste: condi-tioning to disposal; 10. Preparation for the decommissioning of fueldamaged plants; 11. Conclusions; Annex A: Nuclear Power PlantA-1 (Czechoslovakia) experience.


OPERATION OF SPENT FUEL STORAGE FACILITIES:A Safety StandardSafety Series No. 117

This guide has been developed through a series of technical meet-ings and represents an international consensus on useful operatingprinciples. These principles incorporate features which will be effec-tive in maintaining fuel subcritical, removing residual heat, provid-ing radiation protection and containing radioactive materials for thelifetime of the facility. It is intended for use by the nuclear powerindustry, its supporting organizations and related regulatory bodiesin identifying and managing all relevant issues on the operationalaspects for the safe interim storage of spent fuel from nuclear powerplants. It complements Safety Series No. 116, Design of Spent FuelStorage Facilities, and Safety Series No. 118, Safety Assessment forSpent Fuel Storage Facilities.

Contents: 1. Introduction; 2. Key operational activities; 3. Basicsafety considerations for operation; 4. Management; 5. Training andqualifications; 6. Commissioning; 7. Operational limits and condi-tions; 8. Operating procedures; 9. Maintenance, testing, examinationand inspection; 10. Radiation and environmental protection;11. Quality assurance; 12. Safeguards and physical protection;13. Decommissioning; Definitions.


OPTIONS, EXPERIENCE AND TRENDS INSPENT FUEL MANAGEMENTTechnical Reports Series No. 378

Spent fuel management encompasses all the activities associatedwith the handling, transport, storage, processing and eventualdisposal of spent nuclear fuel following its discharge from thereactor. The time-scale for commitment to the safe management ofspent fuel is expected to be several decades, until such time as theeventual disposal arrangements have been engineered. The purposeof this document is to assist Member States to establish policies andnational arrangements for spent fuel management in a structured andtimely manner.

Contents: 1. Introduction; 2. Policy considerations and spent fuelmanagement; 3. Regulatory framework for spent nuclear fuelmanagement systems; 4. Making a choice between options;5. Reprocessing technology; 6. Disposal technology; 7. Storagetechnology; 8. Conclusions.


SAFETY AND ENGINEERING ASPECTS OF SPENT FUEL STORAGEProceedings Series

Proceedings of a symposium jointly organized with OECD/NEA,Vienna, 10–14 October 1994. The purpose of the symposium was toprovide an opportunity for the exchange of information on the stateof the art and the prospects of spent fuel storage, to discuss theworldwide situation and the major factors influencing the nationalpolicies in this field, and to identify the most important directionsthat national efforts and international co-operation in this areashould take.


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Contents: Spent fuel storage programmes; Spent fuel storage tech-nology; Licensing and safety aspects of spent fuel storage; Closingsession; Poster presentations.


SURVEY OF EXPERIENCE WITH DRY STORAGE OF SPENT NUCLEAR FUEL AND UPDATE OF WET STORAGE EXPERIENCETechnical Reports Series No. 290

This report presents data on the dry storage of spent nuclear fuel andrecent information on wet storage, transportation and rod consolida-tion. The amount of spent fuel arisings will increase significantly inthe next one or two decades. In view of the large quantities of spentfuel discharged from nuclear power plants and the expected futuredischarges, many countries are involved in the construction ofstorage facilities and in the development of effective methods forspent fuel surveillance and monitoring to ensure reliable and safeoperation.

Contents: Summary and conclusions; 1. Introduction; 2. Keyconsiderations in the dry storage of zirconium alloy clad fuel;3. Spent fuel description and history; 4. Dry storage technology;5. Spent fuel behaviour during storage; 6. Performance of facilitiesand test programmes; 7. Other experience/developments (wet anddry); 8. Update on wet storage; 9. Transport; Appendix A. Ques-tionnaire, glossary, and acronyms and abbreviations; Appendix B.Special cases; Appendix C. Proposed dry storage facilities; Appen-dix D. Synopsis of USSR experience in spent fuel storage and trans-portation; Appendix E. Detailed description of casks in use andunder development in the USA; Appendix F. Report of BNFL/PNTLand NTL transport flasks (casks) (United Kingdom); Bibliography.


WATER REACTOR FUEL EXTENDED BURNUP STUDYTechnical Reports Series No. 343

(See under Fuel Fabrication and Performance, p. 96)

Waste Management

ADVANCES IN TECHNOLOGIES FOR THE TREATMENT OF LOW AND INTERMEDIATE LEVEL RADIOACTIVE LIQUID WASTESTechnical Reports Series No. 370

This report describes a wide spectrum of treatment processes of bothaqueous and organic radioactive wastes. It briefly covers upgradedtraditional and well proven processes such as chemical precipitation,ion exchange and evaporation, and focuses on rather new membraneand electrochemical processes and combinations of these processes.Methods based on the use of biological processes for the treatmentof liquid radioactive wastes are described in this report for the firsttime. It also describes both advantages and disadvantages of thetechnologies mentioned.

Contents: 1. Introduction; 2. Large scale applications of liquidwaste treatment technologies; 3. Advances in technologies for thetreatment of aqueous wastes; 4. Advances in technologies for the

treatment of organic wastes; 5. Future trends in process develop-ment; Conclusions.


APPLICATION OF EXEMPTION PRINCIPLES TO THE RECYCLE AND REUSE OF MATERIALS FROM NUCLEAR FACILITIES: A Safety PracticeSafety Series No. 111-P-1.1

This Safety Practices publication, part of the lAEA’s RadioactiveWaste Safety Standards (RADWASS) programme, provides guid-ance on the application of internationally agreed principles for deter-mining the levels of radionuclides in materials below which they canbe exempted from regulatory control and can be recycled or reusedwithout any further restriction. It illustrates a methodology by whichpractical exempt quantities for the recycle and reuse of these mate-rials may be derived and gives typical exempt values based on ageneric assessment.

Contents: 1. Introduction; 2. Exemption from regulatory controlapplied to recycle and reuse; 3. Recycle and reuse as options;4. Methods for dose assessment; 5. Recycle scenarios and relatedassumptions; 6. Derived exemption levels; 7. Additional considera-tions and discussion of the results; 8. Summary; References; Appen-dix 1. Methods for estimating individual and collective doses fromexternal exposures to radionuclides during recycle and reuse;Appendix II. Methods for estimating individual and collective dosesfrom inhalation and ingestion of radioactive materials; Appendix III.Estimated individual and collective effective dose equivalents byscenario and pathway for concentrations of 1 Bq/g of each referenceradionuclide for the recycle and reuse of contaminated materials.


APPLICATION OF REMOTELY OPERATED HANDLING EQUIPMENT IN THE DECOMMISSIONING OF NUCLEAR FACILITIESTechnical Reports Series No. 348

This report provides an overview of the state of the art of remotelyoperated handling equipment, notably robotics, in decommission-ing, which is indispensable to reducing personnel radiation exposureand to ensuring the operational reliability of nuclear systems. Inmany situations such tools are the only means of performing a largevariety of decommissioning tasks in environments hostile orinaccessible to humans.

Contents: 1. Introduction; 2. The need for remotely operatedhandling equipment; 3. Selection and design of remotely operatedhandling equipment; 4. Available equipment; 5. Remotely operatedhandling equipment in operating nuclear facilities; 6. Remotelyoperated handling equipment in decommissioning; 7. Remotelyoperated handling equipment for on-site cleanup and decommis-sioning after a severe accident; 8. Design of nuclear facilities for theuse of remotely operated handling equipment for decommissioning;9. Conclusions; Annex I: Belgium; Annex II: Canada; Annex III:France; Annex IV: Germany; Annex V: India; Annex VI: Italy;Annex VII: United Kingdom; Annex VIII: Commission of the Euro-pean Communities.


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ASSESSMENT AND COMPARISON OF WASTE MANAGEMENT SYSTEM COSTS FOR NUCLEAR AND OTHER ENERGY SOURCESTechnical Reports Series No. 366

This report summarizes the results and conclusions of a survey,carried out by the IAEA, of existing waste management costestimates for representative nuclear and fossil fuel cycles with theobjective of providing a correct perspective of the economic andenvironmental aspects of the different means of electricity produc-tion. For the first time waste management cost estimates for all fuelcycle activities from mining to decommissioning of facilities havebeen compiled, and levelized unit costs for waste management havebeen compared to the total levelized costs for electricity production.

Contents: 1. Introduction; 2. Description of fuel cycles; 3. Wastearisings; 4. Waste management; 5. Methodology for cost assess-ment; 6. Cost data; 7. Impact of waste management costs on elec-tricity prices; 8. Comparison of impact of fossil and nuclear wastemanagement costs on electricity prices; 9. Conclusions; Appendix I:Review of available references on fossil waste management costestimates; Appendix II: Source data for nuclear waste managementcosts; Appendix III: Spreadsheet for reference data.


BACK END OF THE NUCLEAR FUEL CYCLE: STRATEGIES AND OPTIONSProceedings Series

(See under Spent Fuel Management, p. 96)

BITUMINIZATION PROCESSES TO CONDITION RADIOACTIVE WASTESTechnical Reports Series No. 352

The aim of this report is to review and evaluate the accumulatedexperience in the use of bituminization techniques for theimmobilization of radioactive wastes, including the description ofincidents which have happened at bituminization facilities, and togive an assessment on the role of bituminization processes in thestrategy for radioactive waste management.

Contents: 1. Introduction; 2. Characterization of bitumens used forwaste immobilization; 3. Types of radioactive wastes suitable forimmobilization in bitumen; 4. Immobilization processes: Opera-tional and safety aspects; 5. Properties of bituminized waste forms;6. Conclusions; Annex: Application of bituminization processes insome Member States.


CHARACTERIZATION OF RADIOACTIVE ➜NEWWASTE FORMS AND PACKAGESTechnical Reports Series No. 383

This report provides guidance on the determination and verificationof key waste characteristics and covers all parameters of wasteforms and packages needed to certify compliance with a specificdisposal scenario. It describes the different methods available for thecharacterization of chemical, physical and biological waste proper-ties as well as of properties related to radioactivity, indicating theadvantages and disadvantages of each individual method. The reportaddresses characterization of all types of radioactive waste exceptfor spent fuel intended for direct disposal.

Contents: 1. Introduction; 2. Categories of waste forms and pack-ages; 3. Basis for waste characterization; 4. Important parameters ofwaste packages; 5. Overview of the characterization process;6. Sampling; 7. Characteristics related to radioactivity; 8. Chemicalcharacteristics; 9. Physical characteristics; 10. Mechanical charac-teristics; 11. Thermal characteristics; 12. Biological properties;13. Conclusions.


CHEMICAL PRECIPITATION PROCESSES FOR THE TREATMENT OF AQUEOUS RADIOACTIVE WASTETechnical Reports Series No. 337

The purpose of this report is to provide a review of chemicalprecipitation processes for the treatment of low and intermediatelevel aqueous waste. It supersedes Technical Reports Series No. 89,Chemical Treatment of Radioactive Wastes, published in 1968. Itprovides data on the performance of existing plants and on improvedprocesses that are in an advanced state of development.

Contents: 1. Introduction; 2. Waste segregation and characteriza-tion; 3. Chemical and adsorptive precipitation and flocculation;4. Examples of chemical treatment facilities; 5. Process selection;6. Process equipment; 7. Sludge conditioning; 8. Concludingremarks.


CLASSIFICATION OF RADIOACTIVE WASTE: A Safety GuideSafety Series No. 111-G-1.1

This Safety Guide, published under the IAEA’s Radioactive WasteSafety Standards (RADWASS) programme, outlines variouspossibilities for the development of a classification system forradioactive wastes. It proposes a modified classification system withgeneral quantitative boundaries and gives guidance for the develop-ment of quantitative classification systems.

Contents: 1. Introduction; 2. Approaches to radioactive waste clas-sification; 3. Proposal for a radioactive waste classification system;Annex: Origin and types of radioactive waste; Glossary.


CLEANUP AND DECOMMISSIONING OF A NUCLEAR REACTOR AFTER A SEVERE ACCIDENTTechnical Reports Series No. 346

The objective of this report is to provide an overview of factors rele-vant to the identification of cleanup requirements and to the choiceof a decommissioning option for a severely damaged nuclear powerplant. It proposes a methodology for the evaluation of variousoptions and the selection of appropriate action in a particular acci-dent situation.

Contents: 1. Introduction; 2. Management after a severe reactoraccident; 3. Factors relevant to cleanup and decommissioning aftera severe accident; 4. Strategy for cleanup; 5. Strategy for decom-


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missioning; 6. Methodology for selection of the preferred decom-missioning option; 7. Conclusions and recommendations; Annex A:Review of four accidents.


CLEANUP OF LARGE AREAS CONTAMINATED AS A RESULT OF A NUCLEAR ACCIDENTTechnical Reports Series No. 300

Experience at Chernobyl showed that the main long term radiologi-cal consequence to the population will probably be external expo-sure from radiaoctive fallout deposited on the ground. The presenttext provides an overview of the methodology and technology avail-able for cleaning up large areas and gives preliminary guidance onthe planning, implementation and management of such cleanups.

Contents: 1. Introduction; 2. Purposes of the report; 3. Scope;4. Planning the cleanup; 5. Managing the cleanup; 6. Characterizingthe affected area; 7. Deposition of contamination on surfaces;8. Characterizing the contamination; 9. Stabilization of contamina-tion; 10. Decontamination techniques and equipment; 11. Interdic-tion of an area; 12. Application of cleanup technology to situationsinvolving high radiation fields; 13. Loading and transporting largevolumes of wastes; 14. Disposal of large volumes of wastes;15. Radiation protection and safety; 16. Conclusions and recom-mendations; Annex A. The cleanup after the accident at the Cher-nobyl nuclear power plant.


CONDITIONING OF ALPHA BEARING WASTESTechnical Reports Series No. 326

The objective of this report is to present state of the art informationon assessments of the complex options available in the managementof alpha bearing wastes from the reprocessing of spent fuels andMOX fuel fabrication.

Contents: 1. Introduction; 2. Alpha bearing wastes: Types and char-acteristics; 3. Matrix materials; 4. Immobilization processes;5. Waste form properties; 6. Packaging the final waste form; 7. Inte-grated alpha bearing waste conditioning facilities; 8. Conclusions.


CONTAINERS FOR PACKAGING OF SOLID AND INTERMEDIATE LEVEL RADIOACTIVE WASTESTechnical Reports Series No. 355

This report aims to review the main requirements for wastecontainers and to provide advice on the design, fabrication,qualification tests and handling of the different types of containersused in the management of low and intermediate level solid radioac-tive wastes. It contains those requirements to be met in the containerdesign to comply with the waste package acceptance requirementsestablished by the regulatory authorities for handling, storage, trans-port and disposal of radioactive waste. It further highlights theimportance of international standardization for waste containerrequirements, which would facilitate the use of common handlingsystems and allow operating experience and performance data to bereadily interchangeable.

Contents: 1. Introduction; 2. Role of the container in wastemanagement; 3. Container design requirements; 4. Materials forcontainers; 5. Cost considerations; 6. Quality assurance and control;7. Qualification tests; 8. Conclusions and recommendations; Appen-dix I: Examples of containers; Appendix II: Corrosion assessmentsof metallic containers; Appendix III: Specification of a test forthermal cycling resistance in France; Appendix IV: A qualificationprocedure for fibre reinforced concrete containers in France.


DECOMMISSIONING OF FACILITIES FOR MINING AND MILLING OF RADIOACTIVE ORES AND CLOSEOUT OF RESIDUESTechnical Reports Series No. 362

(See under Uranium Ore Processing, p. 94)

DECOMMISSIONING OF NUCLEAR FACILITIES ➜NEWOTHER THAN REACTORSTechnical Reports Series No. 386

This is the first IAEA publication dealing specifically with thedecommissioning of non-reactor nuclear facilities. It applies partic-ularly to the nuclear fuel cycle, including uranium conversion,enrichment and fuel fabrication facilities, reprocessing plants, andwaste/spent fuel storage and treatment facilities, but also includesanalytical and research laboratories. It highlights distinctive factorsin the decommissioning of non-reactor nuclear facilities ascompared to those for reactors and offers results from past, ongoingand planned decommissioning activities.

Contents: 1. Introduction; 2. Overview of non-reactor nuclear facil-ities; 3. Basic safety and radiological protection; 4. Decom-missioning strategy and planning; 5. Decommissioning techniquesand equipment; 6. Design and operational features to simplifydecommissioning; 7. Decommissioning experience; 8. Conclusions;Appendix I: Shut down non-reactor nuclear facilities; Appendix II:Detailed data from various non-reactor nuclear facilities decommis-sioning projects; Annex: Problems encountered and lessons learnedfrom decommissioning of selected non-reactor nuclear facilities;References; Bibliography; Glossary.

STI/DOC/010/386 (205 pp., 44 figures; 1998)ISBN 92–0–100998–4srice: 680 Austrian schillings (€49.42)

DECOMMISSIONING TECHNIQUES FOR RESEARCH REACTORSTechnical Reports Series No. 373

This is the first report published by the IAEA which provides guid-ance on the preparation and implementation of the decommissioningof different types of research reactor. Different construction andoperational features of research reactors have a major impact on thedecommissioning techniques required. This report offers informa-tion on the conclusions drawn from a number of completed projectsand identifies their similarities and differences. It is complementedby a computerized research reactor databank. Staff requirements,decommissioning costs, radionuclide inventory, collective expo-sures, waste volumes and waste activity are presented graphicallyaccording to reactor thermal power and integrated energy.

Contents: 1. Introduction; 2. Classification of research reactors;3. Responsibilities and stages of decommissioning; 4. Planningand management of decommissioning; 5. Regulatory aspects;6. Technical aspects applicable to all types of research reactor;

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7. Considerations specific to different types of research reactor;8. Safety aspects; 9. Waste management; 10. Quality assurance;11. Summary and conclusions; Appendix I: Reported researchreactor decommissioning projects; Appendix II: Detailed datafrom research reactor decommissioning projects; Appendix III:Examples of the lessons learned from research reactor decommis-sioning projects.


DESIGN AND OPERATION OF OFF-GAS CLEANING ANDVENTILATION SYSTEMS IN FACILITIES HANDLING LOW ANDINTERMEDIATE LEVEL RADIOACTIVE MATERIALTechnical Reports Series No. 292

Ventilation and air cleaning systems are a vital part of the generaldesign of any nuclear facility. The combination of a well designedventilation system with thorough cleaning of exhaust air is the mainmethod of preventing radioactive contamination of the air inworking areas and in the surrounding atmosphere. This reportprovides the latest information on the design and operation of off-gas cleaning and ventilation systems for designers and regulatoryauthorities in the control and operation of such systems in nuclearestablishments.

Contents: 1. Scope; 2. General purposes of off-gas cleaning andventilation systems; 3. Health and safety requirements for design ofoff-gas cleaning and ventilation systems in nuclear facilities;4. System design; 5. Typical containment, ventilation systems andcomponents; 6. Filter properties; 7. Filter testing methods;8. Conclusions; Annex: Standards and Rules.


DESIGN AND OPERATION OF OFF-GAS CLEANING SYSTEMS AT HIGH LEVEL LIQUID WASTE CONDITIONING FACILITIESTechnical Reports Series No. 291

The immobilization of high level liquid wastes from the repro-cessing of irradiated nuclear fuels is of great interest, and seriousefforts are being undertaken to find a satisfactory technical solution.Volatilization of fission product elements during immobilizationposes the potential for the release of radioactive substances to theenvironment and necessitates effective off-gas cleaning systems.This report describes typical off-gas cleaning systems used in themost advanced high level liquid waste immobilization plants andconsiders most of the aerosols and volatile contaminants.

Contents: 1. Introduction; 2. Nature of high level liquid waste(HLLW); 3. HLLW solidification processes and their application;4. Sources and characteristics of off-gas contaminants; 5. Equipmentused in off-gas treatment systems; 6. Typical off-gas systems andtheir performance; 7. Safety considerations; 8. Conclusions.


DESIGN OF OFF-GAS AND AIR CLEANING SYSTEMS AT NUCLEAR POWER PLANTSTechnical Reports Series No. 274

This report is aimed at: (a) quantifying airborne radionuclides in off-gas and ventilation air streams in nuclear power plants;

(b) reviewing the current status and latest development trends indesign for normal operation and design basis accidents; (c) provid-ing guidelines for design.

Contents: Introduction; General design principles; LWR nuclearpower plants; Other types of reactors; Trends in off-gas and aircleaning system design; References; Appendix A.I: Source termspecifications for LWRs; Appendix A.ll: Examples of calculationsusing the GALE code.



The problem of ground contamination in the case of a severe nuclearaccident is one of special concern. This report gives guidance on theplanning and management of safe transportation and disposal oflarge volumes of contaminated materials, with the objectve of mini-mizing the consequences of such an accident. It is closely linked toTechnical Reports Series No. 300, Cleanup of Large Areas Contam-inated as a Result of a Nuclear Accident (1989), and No. 327, Plan-ning for Cleanup of Large Areas Contaminated as a Result of aNuclear Accident (1991).

Contents: 1. Introduction; 2. Purpose; 3. Scope; 4. Waste charac-teristics and quantities; 5. Treatment of wastes; 6. Scenarios for thetransportation and disposal of wastes; 7. Loading and transportationof large volumes of waste; 8. Disposal of large volumes of waste;9. Disposal facility operation, closure and surveillance; 10. Reviewof operational experience; 11. Radiation protection and safety plan;12. Conclusions; Appendix A. Radiological criteria required toimplement the cleanup of large areas after an accident at a nuclearfacility; Appendix B. A generic method for estimating costs of wasteloading, transportation and disposal; Appendix C. Experience inCanada with the transportation and long term management ofradioactively contaminated soils; Appendix D. Experience in theUSA with the transportation and disposal of radium contaminatedwaste; Appendix E. Transportation and disposal of large volumes ofcontaminated material arising from cleanup after the Chernobylaccident.


EVALUATION OF SPENT FUEL AS A FINAL WASTE FORM Technical Reports Series No. 320


FACTORS RELEVANT TO THE RECYCLING OR REUSE OF COMPONENTS ARISING FROM THE DECOMMISSIONING AND REFURBISHMENT OF NUCLEAR FACILITIESTechnical Reports Series No. 293

The decommissioning and decontamination of nuclear facilities is atopic of interest because of the large number of older nuclear facili-ties which are, or soon will be, retired from service. This publicationprovides a review of the engineering, social, scientific and adminis-


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trative factors relevant to the safe recycling or reuse of componentsarising from decommissioning or refurbishment of nuclear facilities.

Contents: 1. Introduction; 2. Scope; 3. Recycling in industry;4. Recycling or reuse of nuclear components; 5. Decontami-nationfor recycling or reuse; 6. Factors to be considered in the recycling orreuse of components; 7. Life extension of facilities; 8. Safety inrecycling or reuse; Summary and conclusions; Annex: Monitoringfor compliance with release criteria.


FEASIBILITY OF SEPARATION AND UTILIZATION OF CAESIUM AND STRONTIUM FROM HIGH LEVEL LIQUID WASTETechnical Reports Series No. 356

This is the first report reviewing some of the aspects of the recoveryand utilization of caesium and strontium from high level waste andthe consequent impacts on high level waste management strategy.

Contents: 1. Introduction; 2. Current and future arisings of 137Csand 90Sr from spent nuclear fuel; 3. Potential applications for 137Csand 90Sr; 4. Impact of fission product separation on high level wastemanagement; 5. Methods for recovery and immobilization of 137Csand 90Sr; 6. Economic aspects; 7. Public acceptability of radiationsources; 8. Conclusions; Appendix: Some aspects of solvent extrac-tion methods for caesium and strontium recovery from HLW.


FEASIBILITY OF SEPARATION AND UTILIZATION OF RUTHENIUM, RHODIUM AND PALLADIUM FROM HIGH LEVEL WASTESTechnical Reports Series No. 308

The fission product nuclides generated during the irradiation ofreactor fuel include several useful materials, among them preciousmetals of the platinum group (ruthenium, rhodium and palladium)which are of great commercial importance, occur rarely in natureand are highly valuable. This report is intended mainly to provide abasis for further consideration of the options for platinum groupmetal recovery from high level radioactive wastes, and for theformulation of appropriate strategies.

Contents: 1. Introduction; 2. Properties, uses and markets for plat-inum group metals; 3. Production of platinum group metals innuclear reactors: Composition, cooling effects and amounts arising;4. Occurrence of platinum group metals in nuclear fuel cycle opera-tions; 5. Recovery and purification of platinum group metals fromnuclear fuel reprocessing wastes; 6. Radiation safety and licensingconsiderations; 7. Conclusions and recommendations.


GEOLOGICAL DISPOSAL OF SPENT FUEL AND LEVEL HIGH AND ALPHA BEARING WASTESProceedings Series


IMMOBILIZATION OF LOW AND INTERMEDIATE LEVELRADIOACTIVE WASTES WITH POLYMERSTechnical Reports Series No. 289

The conversion of treated radioactive wastes by solidification toobtain stable forms is an important step in waste managementbecause in this way the potential for radioactivity release to the envi-ronment during storage, transportation and disposal can be mini-mized. This report reviews current practices in the immobilization oflow and intermediate level radioactive wastes with polymers as wellas new and promising research and development in this field. Somebackground information on the properties of polymers is given.

Contents: 1. Introduction; 2. Characteristics and sources of low andintermediate level radioactive wastes; 3. Characterization of poly-mers; 4. Pre-treatment of wastes before immobilization; 5. Immobi-lization processes; 6. Conclusions.


IMPROVED CEMENT SOLIDIFICATION OF LOW AND INTERMEDIATE LEVEL RADIOACTIVE WASTESTechnical Reports Series No. 350

This report provides an explanation of the chemistry of cementationsystems and assistance in facilitating the choice of solidificationagents and processing equipment. It reviews recent developments incementation technology for improving the quality of cementedwaste forms and gives a brief description of the various cementsolidification processes in use.

Contents: 1. Introduction; 2. Waste characterization; 3. Charac-terization of cement for solidification of waste; 4. Cementadmixtures; 5. Chemical aspects of waste cementation; 6. Cementsolidification processes; 7. Properties of immobilized waste forms.


INTERIM STORAGE OF ➜NEWRADIOACTIVE WASTE PACKAGESTechnical Reports Series No. 390

This report reviews past and current experience and provides valu-able technical guidance on the production and interim storage ofradioactive waste packages.

Contents: 1. Introduction; 2. Safety principles and requirements forwaste package storage; 3. Production of waste packages; 4. Storagefacilities; 5. Operational experience and optimal storage practices;6. Waste package management options after the licensed storageperiod; 7. Recommended measures to ensure optimal performanceof waste packages during storage; 8. Conclusions; Appendix:Storage facilities in selected Member States.


INTERNATIONAL CO-OPERATION ON NUCLEAR WASTEMANAGEMENT IN THE RUSSIAN FEDERATION

Proceedings of a seminar organized at the request of the NordicStates, Vienna, 15–17 May 1995, with the purpose of encouraginggreater international co-operation with the Russian Federation in thearea of radioactive waste management. This publication provides to


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the international community the first comprehensive picture of thewaste management infrastructure of the Russian Federation and mayassist countries and organizations that wish to begin or extend co-operative programmes in this area. To this end the IAEA will estab-lish an international Expert Contact Group to co-ordinate and assistsuch programmes.

Contents: Opening speeches; Presentations by the Russiandelegation; Presentations from countries and internationalorganizations having co-operative waste management programmeswith the Russian Federation; Closing summaries.


MANAGEMENT OF ABNORMAL RADIOACTIVE WASTES AT NUCLEAR POWER PLANTSTechnical Reports Series No. 307

This report discusses the management of abnormal wastes at nuclearfacilities. It is intended to give guidance to nuclear power plant oper-ators on the technical means available to enable abnormal wastes tobe managed safely, and to provide assistance in the selection ofappropriate technologies and processes that can be used for abnor-mal situations. In addition, subjects such as pre-planning and provi-sions for abnormal waste management, decision making on themanagement of abnormal wastes and adequate waste characteriza-tion are also discussed.

Contents: 1. Introduction; 2. Pre-planning; 3. Abnormal wastemanagement decision making and planning; 4. Characterization ofthe wastes; 5. Decontamination; 6. Treatment of liquid wastes;7. Treatment of gaseous wastes; 8. Treatment of solid wastes;9. Conditioning of abnormal radioactive wastes; 10. Storage, trans-port and disposal; References; Annex I. Experience with abnormalwastes and their management in selected power plants; Annex II.Examples of decision making processes in the management ofabnormal wastes.


MANAGEMENT OF LOW AND INTERMEDIATE LEVELRADIOACTIVE WASTES 1988Proceedings Series

Proceedings of a symposium jointly organized with the CEC, Stock-holm, Sweden, 16–20 May 1988. The symposium addressed allmain stages in the management of radioactive wastes, namely treat-ment, conditioning, waste form characterization and disposal. At thesymposium the substantial progress in the development of thesesystems was indicated. In this context the construction of a deeprepository with complementary regulatory arrangements in Swedenwas an important milestone in the establishment of waste manage-ment facilities. The various contributions represent a wide spectrumof problems associated with the management of radioactive wastesin different countries, describe national waste management policiesin Member States, and present new ideas, approaches and problems,for example, problems of management of mixed hazardous wasteswhich contain not only radioactive materials but also other chemi-cally hazardous or aggressive non-radioactive components.

Contents: (Vol. 1) National and international waste managementprogrammes and policies; Disposal options and performance andsafety assessment; Waste characterization, quality control andacceptance criteria; Treatment and conditioning of solid wastes

(including volume reduction); Treatment and conditioning of mixedhazardous wastes and institutional wastes; (Vol. 2) Treatment andconditioning of liquid wastes; Disposal and safety assessment;Waste characterization and acceptance criteria; Treatment andconditioning of radioactive wastes.

STI/PUB/784 (Vol. 1: 459 pp., 92 figures; Vol. 2: 314 pp., 73 figures; 1989)1: ISBN 92–0–020089–32: ISBN 92–0–020189–XPrice: Vol. 1: 1370 Austrian schillings (€99.56)




METHODOLOGY AND TECHNOLOGY OF DECOMMISSIONING NUCLEAR FACILITIESTechnical Reports Series No. 267

This report is a review of the current state of the methodology andtechnology of decommissioning nuclear facilities including remotesystems technology.

Contents: Introduction; Scope; Definitions of the basic stages ofdecommissioning; Considerations affecting decommissioningchoices; Methodology and technology of decommissioning;Decommissioning safety; Facilitation of decommissioning; Infor-mation database; Conclusions and recommendations; Annex A:Inventory of nuclear facilities of interest to decommissioning;Annex B: Disassembly techniques; Annex C: Remotely controlledequipment for decommissioning.


MINIMIZATION OF RADIOACTIVE WASTE FROM NUCLEAR POWER PLANTS AND THE BACK END OF THE NUCLEAR FUEL CYCLETechnical Reports Series No. 377

Waste management at the back end of the nuclear fuel cyclecomprises the various activities involved in the handling of the spentfuel once it has left the reactor. The purpose of the minimization ofradioactive waste is threefold: (a) to reduce the risks of radiationexposure of technical personnel as well as of the public; (b) toreduce contamination of the environment; and (c) to reduce overallcosts by reducing the repository space required for final wastedisposal. Waste minimization has become a major part of wastemanagement policies.

Contents: 1. Introduction; 2. Waste minimization strategy; 3. Typesand quantities of waste generated; 4. Practical waste minimizationachievements; 5. Future trends; 6. Conclusions; References; Appen-dix A: Liquid and wet solid waste minimization techniques inLWRs; Appendix B: Dry solid waste minimization techniques inLWRs; Appendix C: General/administrative waste minimizationtechniques in LWRs.



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MONITORING PROGRAMMES FOR UNRESTRICTED RELEASE RELATED TO DECOMMISSIONING OF NUCLEAR FACILITIESTechnical Reports Series No. 334

The present report was conceived as a technical document in aneffort to achieve international consensus on release criteria for thedecommissioning of nuclear facilities. It provides an overview of allthe factors to be considered in the development, planning and imple-mentation of a monitoring programme to assure regulatory compli-ance with criteria for unrestricted release of materials, buildings andsites from decommissioning.

Contents: 1. Introduction; 2. Purpose and scope; 3. Release criteria;4. Common practices of unrestricted release; 5. Factors to be consid-ered in determining a monitoring programme; 6. Instruments andmethods; 7. Final survey; 8. Quality assurance and documentation;9. Cost of monitoring for compliance; References; Appendix: Statis-tical considerations of the critical level and the detection unit.


OFF-GAS AND AIR CLEANING SYSTEMS FOR ACCIDENTCONDITIONS IN NUCLEAR POWER PLANTSTechnical Reports Series No. 358

Air cleaning systems are subjected to major challenges under acci-dent conditions and the potential large source terms require thehighest environmental protection from atmospheric release. Theobjective of this report is to consider the principles involved and tosurvey existing systems and equipment for the mitigation of theconsequences of abnormal plant operations, including severe acci-dents beyond the design basis. Some experiences under abnormalconditions and international trends in the development of accidentair cleaning are also included.

Contents: 1. Introduction; 2. Source terms; 3. Design principles;4. Control of airborne contamination in design basis accidents;5. Control of airborne contamination in severe accidents; 6. Experi-ence and trends; 7. Conclusions and recommendations; Appendix:Testing of off-gas cleaning equipment for nuclear power plants.


OPERATIONAL MANAGEMENT FOR RADIOACTIVE EFFLUENTS AND WASTES ARISING IN NUCLEAR POWER PLANTS: A Safety GuideSafety Series No. 50-SG-O11

This guide covers the provisions to be made by the operating orga-nization prior to and during the commissioning and operating phasesof a nuclear power plant in order to keep the radiological impact onthe environment and the radiation exposure of the general public aslow as is reasonably achievable. It discusses the main sources ofradioactive wastes and the means available for their minimization,the classification and segregation of these wastes and the wastemonitoring programmes on-site.

Contents: Introduction; Objectives of the waste managementprogramme; Control of waste production; Waste treatment; Wastestorage; Waste transport; Effluent releases and environmental moni-toring; Abnormal conditions; Administration and organization;Annex I. Operating procedures; Annex II. Monitoring parameters ofwaste treatment systems; Annex III. Waste treatment systems.

STI/PUB/734 (52 pp.; 1986)E ISBN 92–0–123686–7C ISBN 92–0–523391–9F ISBN 92–0–223687–9R ISBN 92–0–424188–8S ISBN 92–0–323487–XPrice: 200 Austrian schillings (€14.53)

OPTIONS FOR THE TREATMENT AND SOLIDIFICATION OF ORGANIC RADIOACTIVE WASTESTechnical Reports Series No. 294

Solid and liquid organic radioactive wastes are generated fromnuclear fuel cycle facilities and nuclear research centres, fromcertain uses of radioisotopes in medicine, and from research anddevelopment in other fields. Compared to other radioactive wastes,the volume of organic wastes generated is small; nevertheless theyrequire a waste management strategy for safe handling, processingand final disposal. This report presents a review of the latest techni-cal information available on options for the treatment and condi-tioning of organic radioactive wastes.

Contents: 1. Introduction; 2. Waste characterization; 3. Wastemanagement strategies; 4. Treatment and immobilization options;5. Characterization of conditioned organic wastes; 6. Conclusions.


PARTICULATE FILTRATION IN NUCLEAR FACILITIESTechnical Reports Series No. 325

The removal of particulate radioactive material from exhaust air orgases is an essential feature of virtually all nuclear facilities. RecentIAEA publications have covered the broad designs of off-gas and aircleaning systems for a range of nuclear power plants and other facil-ities. This report is a complementary guidebook that examines indetail the latest developments in the design, operation, maintenanceand testing of fibrous air filters.

Contents: 1. Introduction; 2. Fundamentals of filtration; 3. Cha-racteristics of filtration systems; 4. Use of aerosol filters in nuclearfacilities; 5. Ventilation and filter systems; 6. Handling, inspectionand installation of new filter inserts; 7. Filter testing; 8. Handling,storage and disposal of contaminated filter inserts; 9. Trends anddevelopments.


PERFORMANCE OF ENGINEERED BARRIERS IN DEEP GEOLOGICAL REPOSITORIESTechnical Reports Series No. 342

This report describes the performance of certain types of engineeredbarriers, e.g. backfills for excavated areas, buffers between the wastecontainer and the host rock, and seals for boreholes, shafts anddrifts, in a deep geological repository system for the disposal of highlevel radioactive wastes. In addition, it provides technical informa-tion relevant to their development.

Contents: 1. Introduction; 2. Objectives and scope; 3. Performanceof the backfill and sealing systems and their evaluation;


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4. Repository design concepts; 5. Seal performance functions;6. Laboratory and field testing; 7. Summary and conclusions.


PLANNING AND MANAGEMENT FOR THE DECOMMISSIONING OF RESEARCH REACTORS AND OTHER SMALL NUCLEAR FACILITIESTechnical Reports Series No. 351

This report provides guidance on the proper planning andmanagement for the decommissioning of research reactors and othersmall nuclear facilities. The information contained in the report can,to a large extent, also be applied to the decommissioning of largefacilities.

Contents: 1. Introduction; 2. Scope of the report; 3. Reasons for andstages of decommissioning; 4. Decommissioning planning;5. Decommissioning management; 6. Quality assurance; 7. Wastemanagement; 8. Decommissioning cost and financing; 9. Responsi-bilities and functions of parties in decommissioning; 10. Regulatoryinterfaces; 11. Recommendations for further work; 12. Summary;Annex: Stages of Decommissioning; Glossary.


PLANNING AND OPERATION OF ➜NEWLOW LEVEL WASTE DISPOSAL FACILITIESProceedings Series

Proceedings of a symposium on Experience in the Planning andOperation of Low Level Waste Disposal Facilities, Vienna,17–21 June 1996. During the past 30 to 40 years extensive experi-ence has been gained in planning, siting, designing, licensing,constructing, operating and closing down various types of low levelradioactive waste (LLW) disposal facilities. The purpose of thissymposium was to facilitate the information transfer process onexperience gained. Past disposal practices and attempts to defineadequate approaches for LLW disposal in developing countries wereaddressed at an open discussion. Finding less expensive ways ofmanaging very low level waste, as well as the reassessment of pastdisposal practices, remediation and procedures in the post-opera-tional phase were considered as areas of importance. Difficulties inthe implementation of LLW disposal plans were also discussed.

Contents: Keynote address; Regulation and licensing; Infra-structure and planning; Siting; Disposal systems and operation;Safety assessment; Post-operation; Poster presentations.


PLANNING FOR CLEANUP OF LARGE AREAS CONTAMINATED AS A RESULT OF A NUCLEAR ACCIDENT Technical Reports Series No. 327

This the second of three IAEA publications dealing with the cleanupof large areas contaminated as a result of a nuclear accident. It ismainly a planning and management document, outlining the broadstrategic and tactical approach to cleanup, the management structureand other key requirements. The report also shows how the varioussubplans interface and interact to ensure that cleanup can be

performed safely, efficiently and as quickly as possible underadverse conditions.

Contents: 1. Introduction; 2. Purpose; 3. Scope; 4. Responsi-bilities for emergency planning and management; 5. Planning andmanaging the cleanup; 6. Data management; 7. Geographical co-ordinate grid system; 8. Radiological survey plan; 9. Compliancewith release criteria; 10. Logistic support; 11. Quality assuranceplan; 12. Training and exercises; 13. Updating the preliminarycleanup plan; 14. Radiation protection and safety of workers;15. Summary; Appendix A: Brief review of cleanup methodologyand technology; Appendix B: Examples of data managementsystems which could be applied to the cleanup of large areas.


QUALITY ASSURANCE FORRADIOACTIVE WASTE PACKAGESTechnical Reports Series No. 376

This publication describes requirements for and provides guidance(mostly gained by waste management agencies in the EuropeanUnion and the USA) on quality assurance in the field of radioactivewaste conditioning, from both the technological and regulatorypoints of view. It provides a logical basis for the application ofquality assurance to the waste conditioning process, includingcontainer manufacture, waste immobilization and packaging, and tointerrelated interim storage, transportation and disposal processes,with the purpose of ensuring the level of confidence required by theorganizations concerned.

Contents: 1. Introduction; 2. General principles of qualityassurance in radioactive waste management; 3. Quality assuranceprogramme considerations; 4. Management; 5. Performance;6. Assessment; 7. Conclusions; Appendix I: Selective applicationand the graded approach; Appendix II: Important parameters ofwaste packages; Appendix III: Process control quality plan.


RADIOACTIVE WASTE MANAGEMENT GLOSSARY

The purpose of this glossary is to provide a source of words whichare commonly and internationally used or have special meanings inthe field of radioactive waste management. It should furthercontribute to a common use of terms in the IAEA Radioactive WasteSafety Standards (RADWASS) series. In the context of this glossary,the term ‘waste’ refers, in general, to radioactive waste unless other-wise specified.


RADIOLOGICAL CHARACTERIZATION OF ➜NEWSHUT DOWN NUCLEAR REACTORS FOR DECOMMISSIONING PURPOSESTechnical Reports Series No. 389

This report describes and assesses radiological characterization as aprecursor to decommissioning. It shows the influence of the radioac-tive inventory on the planning and strategies of decommissioningand also presents an extensive overview of characterization resultson various reactors which have been or are being decommissioned.


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Contents: 1. Introduction; 2. Characterization objectives; 3. Healthand safety considerations; 4. Characterization process; 5. The radio-logical inventory; 6. Methods and techniques for characterization;7. Quality assurance requirements; 8. Conclusions; Appendix:Statistics for radiological characterization; Annexes I–1 to I–9:National experience in various Member States; Annex II: Problemsencountered in the characterization of nuclear reactors and lessonslearned.


REPORT ON RADIOACTIVE WASTE DISPOSALTechnical Reports Series No. 349

The purpose of this report is to provide an overview of the currentknowledge in the field of radioactive waste disposal, limiting itselfto the essential topics in this field. It covers the basic principlesassociated with the state of the art of near surface and deep geolog-ical radioactive waste disposal, including examples of prudent prac-tice, and provides basic information on performance assessmentmethods.

Contents: 1. Introduction; 2. Background information; 3. Natureand function of natural barriers; 4. Engineering barriers; 5. Sitingand site characterization; 6. Repository concepts and operation;7. Performance assessment of disposal systems; 8. Regulatory andinstitutional aspects; 9. Conclusion.


SAFE ENCLOSURE OF SHUT DOWN NUCLEAR INSTALLATIONSTechnical Reports Series No. 375

This publication gives a concise description of factors (safety-related, technical and economical) that are relevant to the selectionof a decommissioning strategy, with particular reference to the safeenclosure option as a precursor to the dismantling of a nuclearinstallation. It is complemented by data on selected shut downinstallations. Aspects such as radioactive inventory, reasons for thechosen decommissioning strategy and systems kept operational oron stand-by are highlighted.

Contents: 1. Introduction; 2. Objective; 3. Scope; 4. Structure;5. Considerations influencing the choice of decommissioning strat-egy; 6. General overview of strategies and regulatory considerations;7. Radiological considerations in safe enclosure; 8. Preparation forsafe enclosure; 9. Management of safe enclosure; 10. Public safetyand environmental aspects; 11. Summary and conclusions; Appen-dix: Problems of the application of safe enclosure in relation tovarious plant conditions; Annex A. Description of selected cases ofsafe enclosure.


SAFE MANAGEMENT OF WASTES FROM THE MINING AND MILLING OF URANIUM AND THORIUM ORES:Code of Practice and Guide to the CodeSafety Series No. 85

This publication is an update of IAEA Safety Series No. 44 (1976)necessitated by a number of developments in the technical and regu-latory aspects of the management of wastes resulting from the

mining and milling of uranium and thorium ores. It consists of twoparts: a Code of Practice (Part I) and a Guide to the Code (Part II).The Code sets forth the requirements for the safe and responsiblehandling of the wastes, while the Guide presents further guidance inthe use of the Code together with some discussion of the technologyand concepts involved.

Contents: Part 1. Code of Practice: 1. Introduction; 2. Objective;3. Scope; 4. Definitions; 5. Wastes from the mining and milling ofradioactive ores, their radiological impact and control by wastemanagement; 6. Principles of radiological protection; 7. Respon-sibilities; 8. Design of waste management facilities; 9. Collection,storage and treatment of wastes; 10. Operation of wastemanagement facilities; 11. Decommissioning of mines, mills andwaste management facilities; 12. Monitoring, surveillance andmaintenance. Part 2. Guide to the Code: 1. Introduction; 2. Objec-tive; 3. Scope; 4. Definitions; 5. Wastes from the mining and millingof radioactive ores, their radiological impact and control by wastemanagement; 6. Principles of radiological protection; 7. Responsi-bilities; 8. Design of waste management facilities; 9. Collection,storage and treatment of wastes; 10. Operation of waste manage-ment facilities; 11. Decommissioning of mines, mills and wastemanagement facilities; 12. Monitoring, surveillance and mainte-nance; References.

STI/PUB/772 (70 pp., 2 figures; 1987)E ISBN 92–0–123587–9F ISBN 92–0–224188–0R ISBN 92–0–423689–2S ISBN 92–0–323488–8Price: 260 Austrian schillings (€18.89)

SEALING OF UNDERGROUND REPOSITORIES FOR RADIOACTIVE WASTESTechnical Reports Series No. 319

For high level and alpha bearing radioactive wastes, the disposalconcept most generally agreed upon is the emplacement of theconditioned waste in deep underground respositories in stablegeological formations. The report reflects the general consensus thatlong lived radioactive wastes can be isolated safely from humanenvironment in such repositories located in deep, geological forma-tions. One of the most important tasks in the development of under-ground disposal systems is the plugging of boreholes and the sealingof shafts excavated for either exploratory or operational purposes.Several countries have outlined proposals and identified geologicalformations for detailed examination as potential host media forwaste repositories.

Contents: 1. Introduction and scope; 2. Background information;3. Performance specifications; 4. Materials and methods;5. Longevity; 6. Design factors; 7. Design of sealing systems;8. Performance testing; References; Glossary.


SITING, DESIGN AND CONSTRUCTION OF UNDERGROUNDREPOSITORIES FOR RADIOACTIVE WASTESProceedings Series

Proceedings of a symposium held in Hannover, Germany,3–7 March 1986. The purpose was to review advances made in thearea of siting, design and construction of underground repositoriesfor radioactive wastes and to consider developments which are offuture importance. Forty-nine papers were presented, coveringgeneral approaches and regulatory aspects, disposal in shallowground and rock cavities, disposal in deep geological formations andsafety assessments.


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Contents: Keynote address: Are we ready to construct and operatean underground repository? General approaches and regulatoryaspects; Disposal in shallow ground and rock cavities; Disposalin deep formations: Investigations on sites; Disposal in deepformations: Repository designs; Safety assessment; Panel: Perfor-mance and safety assessments and their interactions with field inves-tigations of deep geological repositories; Overview of symposium.


SITING OF GEOLOGICAL DISPOSAL FACILITIES: A Safety GuideSafety Series No. 111-G-4.1

This Safety Guide, published under the IAEA’s Radioactive WasteSafety Standards (RADWASS) programme, defines the process tobe used and guidelines to be considered in selecting sites for deepgeological disposal of radioactive wastes. It also addresses thesocial, economic and environmental factors to be considered in siteselection. All data needed for the application of the guidelines arealso specified.

Contents: 1. Introduction; 2. Safety approach; 3. The siting process;4. Site selection guidelines and data needs; Glossary.


SITING OF NEAR SURFACE DISPOSAL FACILITIES:A Safety GuideSafety Series No. 111-G-3.1

This Safety Guide defines the site selection process and criteria foridentifying suitable near surface disposal facilities. It providesguidelines for the siting process management and specifies the dataneeded to apply the relevant selection criteria.

Contents: 1. Introduction; 2. Approach to siting; 3. Management ofthe siting process; 4. Siting guidelines and data needs.


STATE OF THE ART TECHNOLOGY FOR ➜NEWDECONTAMINATION AND DISMANTLINGOF NUCLEAR FACILITIESTechnical Reports Series No. 395

This report is a review of the current state of the art of technologiesused for the decommissioning of nuclear facilities, including tech-nologies for decontamination and dismantling, waste managementand remote systems. It summarizes practical experience gained overthe last 10 to 15 years in the field of decommissioning.

Contents: 1. Introduction; 2. Purpose and scope; 3. Structure;4. Factors to be considered in the selection and implementation of adecommissioning strategy; 5. Safety and radiation protection;6. Methods and technologies for decommissioning; 7. Generallessons learned; 8. Conclusions; Appendix.


STATUS OF TECHNOLOGY FOR VOLUME REDUCTION AND TREATMENT OF LOW AND INTERMEDIATE LEVEL SOLID RADIOACTIVE WASTETechnical Reports Series No. 360

This report describes all existing methods of treatment of solid, lowand intermediate level radioactive waste: mechanical, thermal,melting, chemical, biological and photochemical processes; bothestablished proven technologies and advanced methods. It furtherdiscusses the treatment of generated liquid, solid and gaseoussecondary waste. Comprehensive references on the subject are alsogiven.

Contents: 1. Introduction; 2. Waste treatment objectives and strate-gies; 3. Sources and types of waste; 4. Pretreatment of solid radioac-tive waste; 5. Mechanical treatment; 6. Thermal treatment processes;7. Melting and sintering processes; 8. Chemical, biological andphotochemical treatment processes; 9. Decontamination of equip-ment and components; 10. Conditioning of processed primarywastes; 11. Secondary waste treatment.


TREATMENT, CONDITIONING AND DISPOSAL OF IODINE-129Technical Reports Series No. 276

The evaluation of optimum waste management practices for the longlived iodine-129 has received special consideration with the expan-sion of nuclear power programmes. Radioiodine can be removedfrom off-gas streams by a variety of physical, chemical or physico-chemical processes. This publication reviews the various techniquescollectively and reports on current developments of the techniquesused in the immobilization of recovered iodine and disposal of theconditioned wastes, with due regard to the radiological hazardsinvolved.

Contents: 1. Introduction; 2. Characteristics and arisings of iodine-129; 3. Monitoring iodine-129; 4. Treatment and conditioning ofiodine-129 in nuclear fuel reprocessing; 5. Disposal options andassociated radiological impacts; 6. Radiological significance ofiodine-129 in disposal of unreprocessed spent fuel; 7. Cost ofiodine-129 management; 8. Conclusions and recommendations.

STI/DOC/10/276 (84 pp.; 1987)

ISBN 92–0–125287–0Price: 280 Austrian schillings (€20.35)

TREATMENT OF ALPHA BEARING WASTESTechnical Reports Series No. 287

The report reviews developments in the field aiming at the improve-ment of the dissemination and exchange of the most up to date tech-nology. It discusses topics such as alpha waste management activi-ties, including sources and types of wastes, treatment of liquid andsolid wastes, and examples of industrial scale alpha treatmentfacilities.

Contents: 1. Introduction; 2. Sources, types, and volumes of alphabearing wastes; 3. Waste management strategies; 4. Treatment ofsolid alpha bearing wastes; 5. Treatment of liquid alpha bearingwastes; 6. Alpha bearing waste treatment facilities; 7. Conclusionsand recommendations.



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TREATMENT OF OFF-GAS FROM RADIOACTIVE WASTE INCINERATORSTechnical Reports Series No. 302

The field of gaseous effluent treatment systems for incinerators iswide ranging. Efficient treatment systems extract contaminated airprocess gases and retain them by physical or chemical means. Off-gas cleaning systems have been developed to a high technical stan-dard. The primary purpose of this publication is to describe thecurrent design of off-gas cleaning technologies used in incineratorfacilities for low level solid and liquid wastes.

Contents: 1. Introduction; 2. Waste characteristics; 3. Incineratortypes and characteristics of off-gas streams; 4. Environmental andregulatory considerations; 5. General descriptions of technologiesfor off-gas treatment; 6. Component design aspects and performancecharacteristics; 7. Summary of individual systems and operationalexperience; 8. Safety and operational upset conditions; 9. Problemsand development needs; 10. Conclusions; Appendix A: Individualsystems and operational experience.



PLASMA PHYSICS AND NUCLEAR FUSION

A T O M I C A N D P L A S M A – M A T E R I A LI N T E R A C T I O N D A T A F O R F U S I O N

The purpose of this series of annually published volumes of whichthe earlier issues were supplements to the Nuclear Fusion journal isto make available original contributions and review articlescontaining high quality data on the atomic and plasma–materialinteraction processes of interest to thermonuclear fusion research.The scientific scope of the series includes the topics of elementaryatomic collision processes in fusion plasmas, involving photons,electrons, ions, atoms and molecules, the collision processes ofplasma particles with surfaces of fusion relevant materials, and ther-mophysical material response phenomena related to theplasma–material interactions. The review articles providecomprehensive critical analyses and sets of recommended data for abroader class of interaction processes or thermophysical responsephenomena. The series represents a medium for direct exchange ofexpert assessed or generated atomic and plasma–material interactiondata information between the atomic/material physics and fusionresearch communities.

ATOMIC AND PLASMA–MATERIAL INTERACTION DATA FOR FUSION, Volume 1(Supplement to the journal Nuclear Fusion)

This first volume is devoted to the plasma–material interactionprocesses and contains critical data assessments and data collectionsfor all major particle–surface collision processes related to thepartial recycling, impurity generation and material erosion intokamak fusion devices. Apart from processes induced by particleimpact, plasma–material interaction effects related to off-normalplasma events (e.g. disruptions, runaway electron bombardment) arealso covered in this volume. A summary of the status of data infor-mation on these effects is also provided.



Volume 2 of Atomic and Plasma–Material Interaction Data forFusion is devoted to the atomic and molecular processes takingplace in the edge region of magnetically confined fusion plasmas.The comprehensive review articles included in this volume discussexhaustively the current status of the spectroscopic and collisiondata for fusion plasma edge constituents. The collision processesconsidered include: electron scattering on plasma edge neutrals,electron impact excitation and ionization of atomic and molecularions, particle impact induced dissociative and energy transfer reac-tions involving molecular hydrogen isotopes, heavy particle colli-sion processes and ion–molecule reactions. Radiative losses and

electron cooling rates for carbon and oxygen plasma impurities arealso provided.



Volume 3 of Atomic and Plasma–Material Interaction Data forFusion is devoted to atomic collision processes of helium atoms andof beryllium and boron atoms and ions in fusion plasmas. Most ofthe articles included in this volume are extended versions of thecontributions presented at the IAEA experts meetings on AtomicData for Helium Beam Fusion Alpha Particle Diagnostics and on theAtomic Database for Beryllium and Boron, held in Vienna, June1991, or have resulted from the cross-section data analyses andevaluations performed by the working groups of these meetings. Thevolume contains reviews of the most important classes of collisionprocesses of plasma particles with helium atoms and beryllium andboron ions, and comprehensive sets of recommended cross-sectiondata for these processes.



Volume 4 of Atomic and Plasma–Material Interaction Data forFusion contains the result of a critical data evaluation of the cross-sections of ground state and excited hydrogen atoms colliding withthe basic fusion plasma constituents, the electrons and protons, andwith the multiply charged ions of major plasma impurities. Theprimary purpose of the present volume is to provide a complete setof the collisional data required for the modelling of neutral hydro-gen beam penetration in a thermonuclear fusion plasma.



Volume 5 of Atomic and Plasma–Material Interaction Data forFusion is devoted to a critical review of the physical and thermo-mechanical properties of presently considered candidate plasma-facing and structural materials for next-generation thermonuclear

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fusion reactors. This volume should provide fusion reactor design-ers with a source of critically assessed material properties data,including information on the material response to high heat andparticle fluxes and on the thermohydrodynamic coupling withcoolants. Emphasis is given to the presentation of the most recentresults for plasma-facing reactor materials.

STI/PUB/023/APID/05 (268 pp., 197 figures, 21 x 30 cm; 1994)Price: 350 Austrian schillings (€25.44)


Volume 6 of Atomic and Plasma–Material Interaction Data forFusion includes critical reviews and results of original experimentaland theoretical studies on inelastic collision processes among thebasic and dominant impurity constituents of fusion plasmas. Thefollowing processes are considered: electron impact excitation ofexcited helium atoms, electron impact excitation and ionization ofplasma impurity ions and atoms, electron–impurity–ion recombina-tion and excitation, ionization and electron capture in collisions ofplasma protons and impurity ions with the main fusion plasmaneutron components H, He and H2 (the latter being always presentin the plasma edge or introduced into the plasma by neutral beaminjection for heating, fuelling or diagnostic purposes).


ATOMIC AND PLASMA–MATERIAL ➜NEWINTERACTION DATA FOR FUSION, Volume 7, Part A

Volume 7 of Atomic and Plasma–Material Interaction Data forFusion is devoted to a critical review of the chemical erosion behav-iour of fusion plasma-facing materials, in particular carbon, beryl-lium and tungsten. It is intended to provide fusion reactor designerswith a detailed survey and parametrization of existing, criticallyassessed data for the chemical erosion of plasma-facing materials byparticle impact. This volume is the result of a five year Co-ordinatedResearch Programme on “Plasma-Interaction Induced Erosion ofFusion Reactor Materials” in the period 1992–1997. Part B, whichis in preparation, will provide a critical review and data compilationfor physical sputtering and radiation-enhanced sublimation inducedby fusion plasma particle impact.

Contents: 1. Introduction; 2. Erosion data derived from tokamaks;3. Carbon-based materials: Selected collection of chemical erosiondata; 4. Comprehensive set of chemical erosion data from variouslaboratories; Appendix A: List of abbreviations; Appendix B: List ofanalytical fitting functions.

STI/PUB/023/APID/07/A (277 pp., 35 figures, 21 × 30 cm; 1998)Price: 400 Austrian schillings (€29.07)

ATOMIC AND PLASMA–-MATERIAL ➜NEWINTERACTION DATA FOR FUSION, Volume 8

Volume 8 provides an exhaustive source of information on elasticscattering, momentum transfer and viscosity cross-sections for colli-sions of hydrogenic ions, atoms and molecules, and their isotopes,in the energy range pertinent to fusion reactor divertor plasma andextending (in its low-energy part) to collision conditions that arerelevant for astrophysics. Hydrogen ion–helium atom collisions arealso included in this volume. The reported cross-sections are

obtained from extensive quantum-mechanical calculations and canbe regarded as having very high accuracy.

Contents: Part A: Introduction and theory; Part B: Ion–neutral colli-sion systems; Part C: Neutral–neutral collision systems.


ENERGY FROM INERTIAL FUSION

This publication describes the current scientific, engineering and tech-nological developments in the field of inertial confinement fusion(ICF). It provides an introduction to ICF as well as an overview of thevarious technologies needed for inertial fusion power plant develop-ment. It was compiled by an international group of experts under theauspices of an IAEA Advisory Group on Inertial Fusion Energy andis intended for a large audience, e.g. policy makers, scientists, engi-neers or technologists in other fields, and students.

Contents: 1. Introduction: Inertial fusion energy fundamentals;2. Inertial confinement target physics; 3. IFE power plant designprinciples; 4. Special design issues; 5. Inertial fusion energy devel-opment strategy; 6. Safety and environmental impact; 7. Economicsand other figures of merit; 8. Other uses of inertial fusion; 9. Inter-national activities; Authors.

STI/PUB/944 (457 pp., 146 figures; 1995)ISBN 92–0–100794–9Price: 1320 Austrian schillings(€95.93)

FUSION ENERGY 1996 ➜NEWProceedings Series

Proceedings of the Sixteenth International Conference, formerlycalled the International Conference on Plasma Physics andControlled Nuclear Fusion Research, Montreal, 7–11 October 1996.The papers presented reflect the excellent progress achieved sincethe last conference in Seville 1994. Among many other achieve-ments, the Tokamak Fusion Test Reactor has produced over 10 MWof fusion power, the JT-60U experiment has demonstrated plasmaconditions equivalent to breakeven, the reversed shear mode hasbeen demonstrated, low aspect ratio tokamaks have producedpromising results and plans have been drawn up for powerful newinertial confinement fusion experiments.

Contents: (Vol. 1) Overviews 1; Overviews 2; Concept optimization1; Confinement and particles; Operational limits and disruptions;Divertor experiments; Concept optimization 2; Transport experi-ments; Confinement and waves, disruptions and instabilities; Diver-tor experiments and tokamak concept optimization; (Vol. 2) Helicalsystems; Alternative systems experiments; Helical systems andalternative systems; Transport theory; MHD and energetic particletheory; Divertor edge physics and alternatives; Theory; ITER(Sessions F and FP); (Vol. 3) Inertial confinement 1; Inertialconfinement 2; Inertial confinement (Poster Session); Heating andcurrent drive; Heating and current drive; Reactor studies; Technol-ogy and new devices; Technology, new devices and reactor studies(Poster Session).

STI/PUB/1004 (Vol. 1: 931 pp., 574 figures; Vol. 2: 1003 pp., 489 figures;Vol. 3: 746 pp., 376 figures; 1997)1: ISBN 92–0–100797–32: ISBN 92–0–102997–73: ISBN 92–0–103997–2Price: Vol. 1: 2640 Austrian schillings (€191.86)


P L A S M A P H Y S I C S A N D N U C L E A R F U S I O N

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FUSION REACTOR DESIGN AND TECHNOLOGY 1986Panel Proceedings Series

Proceedings of a Technical Committee meeting and workshop,Yalta, 26 May to 6 June 1986. The purpose of the meeting was: (a)to review and assess the current status and recent progress made infusion reactor experiments, design and technology; (b) to identifythe areas in which work needs to be done in order to progresstowards the goal of commercial fusion power reactors; and (c) toidentify the critical issues in fusion reactor design and technologythat will be important during the next five years.

Contents: (Vol. 1) Fusion programmes; Tokamaks; Non-tokamakreactors and open systems; Inertial confinement concepts; Fission-fusion hybrids; (Vol. 2) Plasma engineering; Nuclear and energytechnologies; Materials developments; System studies and safetyaspects.

STI/PUB/754 (Vol. 2: 523 pp., 149 figures; 1987)1: out of print2: ISBN 92–0–131287–3Price: Vol. 2: 660 Austrian schillings (€47.96)

N U C L E A R F U S I O N J O R N A L , S P E C I A L I S S U E SA N D S U P P L E M E N T S

NUCLEAR FUSION JOURNAL

A journal issued twelve times a year which includes original arti-cles, letters, review papers and comments in the field of controllednuclear fusion. Papers covering the following areas are published:plasma effects; processes and phenomena directly related to fusionresearch; production, heating and confinement of plasmas; applica-tion of experimental and diagnostic techniques to high temperatureplasmas; fusion reactor concepts and closely related technology.Special issues and supplements are published occasionally.

STI/PUB/23 (approx. 1800 pp./year, figures 21×30 cm)ISSN 0029–5515Price: Annual subscription (2000):

9900 Austrian schillings (€719.46)(surface mail and airmail delivery included)Special reduced price for individuals:1200 Austrian schillings (€87.21)(surface mail and airmal delivery included)Price per single issue: 940 Austrian schillings (€69.77)

NUCLEAR FUSION — ➜NEWYOKOHAMA SPECIAL ISSUES

These three special issues of the Nuclear Fusion journal contain arti-cles based on some of the papers presented a the 17th Fusion EnergyConference organized by the IAEA and held in Yokohama, Japan,19–24 October 1998. The articles have been fully refereed. Issue 1contains overview papers, while issues 2 and 3 present articles onmagnetic confinement experiments, plasma heating and currentdrive, ITER EDA, inertial fusion energy, innovative concepts, fusiontechnology and theory.

STI/PUB/023/39/Y1 – Issue 1 (144 pp./figures, 21 x 30 cm; 1999)STI/PUB/023/39/Y2 – Issue 2 (518 pp./figures, 21 x 30 cm; 1999)STI/PUB/023/40/Y3 – Issue 3 (324 pp./figures, 21 x 30 cm; 2000)ISSN 0092–5515Price: Issue 1, 2, 3: 940 Austrian schillings (€69.77) each

Special price for all three issues:2200 Austrian schillings (€159.88)

RECOMMENDED DATA ON ATOMIC COLLISION PROCESSES INVOLVING IRON AND ITS IONS Nuclear Fusion — Special Supplement 1987

This publication contains recommendations given by a group ofexperts who attended an Advisory Group meeting held in Vienna,18–20 September 1985. The purpose of the meeting was to reviewthe available atomic collision data relevant to fusion plasma model-ling, with emphasis on processes involving iron and its ions. Thefourteen experts from five Member States reviewed the status of datain the relevant areas of atomic physics and made specific recom-mendations regarding the use of these data in plasma modellingcalculations.

Contents: R.A. Phaneuf, R.K. Janev, H.T. Hunter: Charge exchangeprocesses involving iron ions; M.S. Pindzola, D.C. Griffin, C.Bottcher, S.M. Younger, H.T. Hunter: Electron impact ionizationdata for the iron isonuclear sequence; A.E. Kingston, M.A. Lennon:Electron excitation rates for iron ions.

STI/PUB/23/SPS/1987 (131 pp., 44 figures, 21 × 30 cm; 1987)ISBN 92–0–139087–4Price: 280 Austrian schillings (€20.35)

WORLD SURVEY OF ACTIVITIES IN ➜NEWCONTROLLED FUSION RESEARCH — 1997 EditionNuclear Fusion — Special Supplement 1997

This is the eighth edition of the World Survey of Activities inControlled Fusion Research, presenting the updated addresses,telecom information and scientific staff of over 300 institutes andorganizations worldwide active in fusion research. Information onthe scientific and engineering programmes is given in the form ofshort descriptions of the main activities.

Contents: List of institutes, alphabetized by country and city; Labo-ratories, scientific staff and summaries of activities; PersonnelIndex.

The document is available as hard copy and CD-ROM.

STI/PUB/023/SPS/1997 (410 pp., 21 × 30 cm; 1997)STI/DAT/023/SPS/1997(CD-ROM)ISBN 92–0–104397–XPrice: 450 Austrian schillings (€32.70)

PLASMA PHYSICS AND CONTROLLED NUCLEAR FUSION RESEARCH 1988Proceedings Series

Proceedings of the Twelfth International Conference, Nice,12–19 October 1988.

Contents: (Vol. 1) Artsimovich memorial lecture and tokamakexperiments; Plasma heating and current drive. (Vol. 2) Magneticconfinement systems; Non-tokamak confinement systems. (Vol. 3)Inertial confinement fusion; Next step concepts (INTOR/ITER);Technology and reactor concepts, including safety and environmen-tal aspects; Fundamental processes and new trends; Summarysession.

STI/PUB/787 (Vol. 1: 775 pp., 433 figures; Vol. 2: 763 pp., 308 figures; Vol.3: 720 pp., 250 figures; 1989)


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1: ISBN 92–0–130089–12: ISBN 92–0–130189–83: ISBN 92–0–130289–4Price: Vol. 1: 1920 Austrian schillings (€139.53)



The proceedings of the Thirteenth International conference, Wash-ington, DC, 29 September to 3 October 1990. The Conference wascharacterized by reports of steady technical progress in research onboth magnetic and inertial confinement fusion, leading towards thelong term goal of producing commercial energy from controlledfusion power generators. Also, major results were reported from thecompletion of the Conceptual Design Activities of the InternationalThermonuclear Experimental Reactor (ITER) project, which hasbeen conducted since 1988 under the auspices of the IAEA. At thetechnical sessions more than 200 papers were presented. Contribu-tions were made on: tokamak experiments; inertial confinement;non-tokamak confinement systems; magnetic confinement theoryand modelling; plasma heating and current drive; ITER; technologyand reactor concepts; and the economic, safety and environmentalaspects of fusion.

Contents: (Vol. 1) Artsimovich memorial lecture and tokamakexperiments; Plasma heating and current drive. (Vol. 2) Magneticconfinement theory and modelling; Non-tokamak confinementsystems; (Vol. 3) Inertial confinement fusion; International ther-monuclear experimental reactor (ITER); Technology and reactorconcepts; Economic, safety and environmental aspects of fusion;Summaries.

STI/PUB/844 (Vol. 1: 865 pp., 420 figures; Vol: 2: 808 pp., 330 figures;Vol. 3: 814 pp., 194 figures; 1991)1: ISBN 92–0–130091–32: ISBN 92–0–130191–X3: ISBN 92–0–130291–6Price: Vol. 1: 2300 Austrian schillings (€167.15)



Proceedings of the Fourteenth International Conference, Würzburg,30 September to 7 October 1992. The conference was characterizedby reports of recent results from all the major fusion facilitiesaround the world, including the milestone experiment at JET inwhich tritium was introduced for the first time into a tokamak fuelmixture. The proceedings include all the technical papers, the perti-nent discussions and five conference summaries.

Contents: (Vol. 1) Artsimovich memorial lecture and tokamakexperiments (Session A). (Vol. 2) Magnetic confinement theory andmodelling (Session D); Non-tokamak confinement systems (SessionC). (Vol. 3) Inertial confinement fusion; ITER and next step devices;Technology and reactor concepts. (Vol. 4) Conference summaries.

STI/PUB/906 (Vol. 1: 791 pp., 386 figures; Vol. 2: 689 pp., 258 figures; Vol. 3: 461 pp., 169 figures; Vol. 4: 77 pp., 27 figures; 1993)

1: ISBN 92–0–101093–12: ISBN 92–0–101193–83: ISBN 92–0–101293–44: ISBN 92–0–101393–0Price: Vol. 1: 2200 Austrian schillings (€159.88)

Vol. 2: 1900 Austrian schillings (€138.08)Vol. 3: 1560 Austrian schillings (€113.37)Vol. 4: 240 Austrian schillings (€17.44)


Proceedings of the Fifteenth International Conference held inSeville, 26 September to 1 October 1994. The conference was char-acterized by valuable scientific results on virtually all aspects ofcontrolled fusion and fusion technology, laying a solid foundationfor continued progress. The proceedings include all the technicalpapers, the pertinent discussions, and five conference summarieswhich are published as a separate volume.

Contents: (Vol. 1) Artsimovich memorial lecture and toroidalconfinement systems (Sessions A1 to A6). Toroidal confinementsystems overview (Session A1); Core plasma physics (Session A2);Heating and current drive (Session A3); Divertor and edge physics(Session A4); Concept optimization (Session A5); Helical systemphysics (Session A6); (Vol. 2) Combined poster session A2/A4(Core plasma physics, and divertor and edge physics); Combinedposter session A3/A5 (Heating and current drive, and concept opti-mization); Combined poster session A6/C (Helical system physics,and pinches and open systems); Pinches and open systems (SessionC); ITER (Session E); New devices, reactors and technology(Session F). (Vol. 3) Inertial confinement fusion; Magnetic confine-ment theory; (Vol. 4) Conference summaries.

STI/PUB/948 (Vol. 1: 809 pp., 448 figures; Vol. 2: 809 pp., 363 figures; Vol. 3: 731 pp., 285 figures; Vol. 4: 65 pp., 9 figures; 1995)1: ISBN 92–0–102295–62: ISBN 92–0–103695–73: ISBN 92–0–103795–34: ISBN 92–0–101895–0Price: Vol. 1: 2280 Austrian schillings (T165.69)

Vol. 2: 2280 Austrian schillings (€165.69)Vol. 3: 2080 Austrian schillings (€151.16)Vol. 4: 280 Austrian schillings (€20.35)


SAFEGUARDS

DESIGN MEASURES TO FACILITATE ➜NEWIMPLEMENTATION OF SAFEGUARDS AT FUTURE WATER COOLED NUCLEAR POWER PLANTS Technical Reports Series No. 392

This report presents guidelines to the designers of water cooledpower reactors which will minimize the impact of IAEA safeguardson plant operations and ensure efficient and effective acquisition ofsafeguards data to the mutual benefit of the Member State, the plantoperator and the IAEA. These guidelines incorporate the IAEA’sexperience in establishing and carrying out safeguards at currentlyoperating nuclear power plants, the ongoing development of safe-guards techniques and the feedback of experience from plant opera-tors and designers on the impact of IAEA safeguards on plant oper-ation.

Contents: 1. Introduction; 2. The IAEA’s safeguards function forcurrent and future nuclear power plants; 3. Summary of the politicaland legal foundations of the IAEA’s safeguards system; 4. The tech-nical objective of safeguards and the supply and use of requireddesign information; 5. Safeguards approaches for nuclear powerplants; 6. Design implications of experience in safeguarding nuclearpower plants; 7. Guidelines for design provisions for future watercooled reactors to facilitate the implementation of safeguards;Appendix I: Summary of information requested in the IAEA’sDesign Information Questionnaire; Appendix II: IAEA safeguardsinstrumentation commonly used for power reactors; Glossary.


I A E A S A F E G U A R D S I N F O R M A T I O N S I E R I E S

IAEA SAFEGUARDS GLOSSARY — 1987 EditionIAEA Safeguards Information Series No. 1

This is a revision of the glossary of safeguards terms published in1980, taking into account the latest developments as well ascomments received since the first version appeared. The glossary isintended to contribute to defining and rationalizing many terms usedfor the purpose of IAEA safeguards, with a view to improving thecommon understanding of such terms within the Internationalcommunity and to providing a quick reference for interested readers.

Contents: 1. IAEA Safeguards: Purpose and objective; 2. Nuclearand non-nuclear material; 3. Nuclear installations and equipment;4. Design of the safeguards approach; 5. Nuclear material accoun-tancy; 6. Measurements and equipment; 7. Statistical concepts;8. Containment and surveillance; 9. Safeguards information, records

and reports; 10. Inspections; Appendix: International instrumentsand other basic documents; Translations of terms into French,Russian, Spanish, German and Japanese; Index.

IAEA/SG/INF/1 (Rev. 1) (155 pp.; 1987)E ISBN 92–0–079087–9R ISBN 92–0–400393–6Price: 380 Austrian schillings (€27.62)

IAEA SAFEGUARDS: GUIDELINES FOR STATES’ SYSTEMS OF ACCOUNTING FOR AND CONTROL OF NUCLEAR MATERIALSIAEA Safeguards Information Series No. 2

This publication is intended to assist Member States in establishing,maintaining and reviewing their States’ System of Accounting forand Control of Nuclear Material (SSAC) and therefore presentsguidelines for the organization and functions of the SSAC withrespect to obligations arising from Safeguards Agreementsconcluded by a State with the IAEA, including the elements of theSystem and the performance required from it at the State and facil-ity levels.

Contents: Introduction; Organization and functional elements at thelevel of a State; SSAC organization and operation at the level of afacility.

IAEA/SG/INF/2 (28 pp.; 1980)E ISBN 92–0–179180–1R ISBN 92–0–400293–XPrice: 100 Austrian schillings (€7.27)

IAEA SAFEGUARDS: AN INTRODUCTIONIAEA Safeguards Information Series No. 3

Outdated, no longer available.

IAEA SAFEGUARDS: AIMS, LIMITATIONS, ACHIEVEMENTS IAEA Safeguards Information Series No. 4


IAEA SAFEGUARDS: SAFEGUARDS TECHNIQUES AND EQUIPMENTIAEA Safeguards Information Series No. 5


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IAEA SAFEGUARDS: IMPLEMENTATION AT NUCLEAR FUEL CYCLE FACILITIESIAEA Safeguards Information Series No. 6

This booklet discusses in a systematic manner the safeguardsconcepts, methods and approaches at various nuclear fuel cyclefacilities.

Contents: Concepts; Methodology; Safeguards approaches; List ofinspection activities; Abbreviations; Bibliography.

IAEA/SG/INF/6 (71 pp.; 1985)ISBN 92–0–179085–6Price: 180 Austrian schillings (€13.08)

INTERNATIONAL NUCLEAR SAFEGUARDS 1994: VISION FOR THE FUTUREProceedings Series

Proceedings of a symposium organized in co-operation with ANS,ESARDA, INMM and the Nuclear Society International (Moscow),Vienna, 14–18 March 1994. Presented at this symposium were: thefindings in Iraq by the Action Team established under UnitedNations Security Council resolutions, South Africa’s decision to jointhe Treaty on the Non-Proliferation of Nuclear Weapons (NPT),details of the IAEA–Argentina–Brazil–ABACC Quadripartite Safe-guards Agreement, and measures following the break-up of theformer USSR into newly independent States. Special emphasis wasgiven to the verification of a State’s declaration as well as detectionof undeclared activities. In addition to covering recent develop-ments, the symposium considered fundamental changes stemmingfrom converging relationships between nuclear arms reductions andthe civil use of plutonium, unattended computer based verificationsystems and other safeguards concepts for the future, and the reviewand extension of the NPT in 1995.

Contents: (Vol. 1) Invited overview papers; National and regionalsystems for accounting and control of nuclear material; Materialaccountancy; Safeguards for uranium enrichment and fuelfabrication facilities; New experience and initiatives; Safeguardsstatistics and data processing; Strengthened and more cost effectivesafeguards; Integrated safeguards systems; Research and develop-ment and analytical measurements. (Vol. 2) Safeguards for pluto-nium facilities; Containment and surveillance technology; Safe-guards for reactors and spent fuel storage facilities; Non-destructiveanalysis measurement techniques; Safeguards approaches, criteriaand evaluation; Safeguards concepts for the future; Member Statessupport programmes; Panel on future directions for internationalsafeguards.

STI/PUB/945 (Vol. 1: 839 pp., 172 figures; Vol. 2: 921 pp., 172 figures;1994)Vol. 1: ISBN 92–0–101994–7Vol. 2: ISBN 92–0–104494–1Price: Vol. 1: 2000 Austrian schillings (€145.35)


NUCLEAR SAFEGUARDS TECHNOLOGY 1986Proceedings Series

Proceedings of the sixth Symposium, Vienna, 10–14 November1986. Development efforts related to safeguards for reprocessingplants constitute over twenty per cent of the papers, while most ofthe remaining deal with non-destructive measurement methods. Theemphasis throughout is on demonstrated equipment field tests ofproposed safeguards methods and other practical considerations.

Contents: (Vol. 1) General papers; Safeguards for reprocessingfacilities; Measurements in reprocessing facilities; Safeguards foruranium enrichment facilities; Statistics of sequential data analysis;Safeguards for MOX and uranium fabrication facilities; Spent fuelmeasurements; Analytical measurements; (Vol. 2) Containment-surveillance technology; Safeguards for reactors or long termstorage facilities; Materials accountancy information systems; NDAmeasurement techniques; Safeguards for heavy water; Generalstatistics; Safeguards philosophy and concepts.

STI/PUB/722 (Vol. 1: 769 pp., 172 figures; Vol. 2: 660 pp.,160 figures; 1987)Vol. 1: ISBN 92–0–070187–6Vol. 2: ISBN 92–0–070287–2Price: Vol. 1: 1900 Austrian schillings (€138.08)


PHYSICAL PROTECTION OF NUCLEAR ➜NEWMATERIALS: EXPERIENCE IN REGULATION, IMPLEMENTATION AND OPERATIONS

Proceedings of a conference, Vienna, 10–14 November 1997, whichaimed at fostering the exchange of information, practices and expe-rience in order to assist States, where appropriate, in upgrading theirprogrammes for the physical protection of nuclear materials andcombating illicit trafficking. It focused on the regimes, equipmentand procedures currently used to minimize the possibilities of unau-thorized removal of nuclear material, whether by terrorists, crimi-nals or facility employees, and to protect against sabotage.



S A F E G U A R D S

LEGAL MATTERS

L E G A L S E R I E S

MULTILATERAL AGREEMENTSLegal Series No. 1

Out of print.

CIVIL LIABILITY FOR NUCLEAR DAMAGELegal Series No. 2

Out of print.

AGREEMENTS REGISTERED WITH THE INTERNATIONALATOMIC ENERGY AGENCY — Eleventh EditionLegal Series No. 3

A list of agreements registered with the IAEA during the wholeperiod of its activities from 1957 to the end of 1993. This listcontains agreements between the Agency and any Member State orMember States, agreements between the Agency and any other orga-nization or organizations, and agreements between Member Stateswhen subject to approval by the Agency.

Contents: Part I: Chronological list of agreements 1957–1993;Part II: Major multilateral agreements for which the IAEA is deposi-tary; Part III: Country Annex; Section listing international and otherorganizations.


INTERNATIONAL CONVENTIONS ON CIVIL LIABILITY FOR NUCLEAR DAMAGE — Revised 1976 EditionLegal Series No. 4

Out of print.

NUCLEAR LAW FOR A DEVELOPING WORLDLegal Series No. 5

Out of print.

INSURANCE FOR NUCLEAR INSTALLATIONSLegal Series No. 6

Reports and documents resulting from a panel of experts convenedin Vienna, 24–28 November 1969.


THE LAW AND PRACTICES OF THE INTERNATIONAL ATOMIC ENERGY AGENCYLegal Series No. 7

A study of the Agency’s written law and its practices, based on offi-cial documents and the author’s direct personal experience as a staffmember of many years.


THE LAW AND PRACTICES OF THE INTERNATIONAL ATOMIC ENERGY AGENCY 1970–1980Supplement 1 to the 1970 Edition of Legal Series No. 7Legal Series No. 7-S1

The first publication (Part A) covering this subject was issuedin 1970 (Legal Series No. 7 — the basic book), written byPaul C. Szasz, who, together with Reinhard H. Rainer, is also co-author of the present book. As the Agency’s work has expanded, theemphasis of its programme components shifted and administrativepractices changed, an update of the study became necessary toensure its continued value as a comprehensive reference tool anddocumentation of the main legal and administrative developments.This updated edition retains the original structure of the basic bookas far as possible to allow consultation of both books seriatim.

Contents: Part B. Structure; Part C. Relationships; Part D. Activi-ties; Part E. Administration; Part F. Legal matters; Part G. Proce-dures; Annex.


EXPERIENCE AND TRENDS IN NUCLEAR LAWLegal Series No. 8

A selection of papers presented at the Seminar on the Developmentof Nuclear Law, Bangkok, 6–11 April 1970, and at the InterregionalTraining Course on the Legal Aspects of Nuclear Energy, Athens,7–18 December 1970.


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INTERNATIONAL TREATIES RELATING TO NUCLEAR CONTROL AND DISARMAMENTLegal Series No. 9

The publication contains the most important treaties, agreementsand conventions in the field of arms control and disarmament.


LICENSiNG AND REGULATORY CONTROL OF NUCLEAR INSTALLATIONSLegal Series No. 10

A selection of papers presented at a Regional Seminar in NuclearLaw for Latin American Countries, Rio de Janeiro, 25–29 June1973, and at the Study Group Meeting on Regulations and Proce-dures for Licensing Nuclear Installations, Athens, 16–20 Decem-ber 1974.


INTERNATIONAL ACCEPTANCE OF IRRADIATED FOOD: LEGAL ASPECTSLegal Series No. 11

Report of an Advisory Group meeting convened by FAO, WHO andIAEA in Wageningen, 28 November–1 December 1977, to considerhow national regulations could be harmonized to facilitate theinternational movement of irradiated food and to revise and updateprevious recommendations concerning the legal aspects of foodirradiation.


CONVENTION ON THE PHYSICAL PROTECTION OF NUCLEAR MATERIALLegal Series No. 12

Out of print.

REGLEMENTATION DES ACTIVITES NUCLEAIRESCollection juridique n°13

Communications présentées au Séminaire interrégional sur le droitnucléaire et la réglementation en matière de sûreté nucléaire tenu àRabat (Maroc) en 1983. Le Séminaire visait à donner aux pays fran-cophones d’Afrique un aperçu global de la réglementation nucléaireet de son évolution dans le contexte des normes, recommandationset conventions internationales s’y rapportant. Les 14 communica-tions présentées par des fonctionnaires du Secrétariat de l’AIEA etdes experts venant de différents Etats Membres et organisationsinternationales s’adressent à tous ceux qu’intéresse le développe-ment du droit nucléaire et les questions d’ordre réglementaire liéesà la mise en oeuvre d’un programme national dans le domaine del’énergie atomique. Les annexes contiennent les textes de deux con-ventions dont l’AIEA est le dépositaire, le texte du Traité sur la non-prolifération des armes nucléaires ainsi que des documentsconcernant le système des garanties de l’AIEA et certaines normeset recommandations établies par l’Agence.

Entièrement en français.

STI/PUB/703 (333 pages; 1986)ISBN 92–0–276086–1Prix: 820 schillings autrichiens (€59.59)

CONVENTION ON EARLY NOTIFICATION OF A NUCLEAR ACCIDENT AND CONVENTION ON ASSISTANCE IN THE CASE OF A NUCLEAR ACCIDENT OR RADIOLOGICAL EMERGENCYLegal Series No. 14

This publication contains the texts of the conventions as adopted andbackground material relating to the process of their negotiation andconclusion.

Contents: Convention on Early Notification of a Nuclear Accident;Convention on Assistance in the Case of a Nuclear Accident or Radi-ological Emergency.

STI/PUB/765 (126 pp.; 1987)E ISBN 92–0–176087–6F ISBN 92–0–276088–8R ISBN 92–0–476090–7S ISBN 92–0–376089–XPrice: 340 Austrian schillings (€24.71)

BILATERAL, REGIONAL AND MULTILATERAL AGREEMENTS RELATING TO CO-OPERATION IN THE FIELD OF NUCLEAR SAFETYLegal Series No. 15

This publication contains the texts of bilateral, regional and multi-lateral co-operation agreements in the field of nuclear safety towhich Member States of the IAEA are a party and which have beensubmitted to the Agency by its Member States for inclusion in thepresent volume.

Contents: Part I contains the bilateral agreements in the languageversion(s) provided by Member States, given in alphabetical orderby name of the Member State party to the agreement. Titles of agree-ments provided in a language other than English have been trans-lated into English, but these English versions have no official status.The Index of Bilateral Agreements lists all titles under each MemberState party to any agreement. Part II consists of regional agreements,while Part III pertains to multilateral agreements relating to co-oper-ation in the field of nuclear safety.


CONVENTION ON NUCLEAR SAFETYLegal Series No. 16

This publication contains the text of the Convention on NuclearSafety, material relating to the process of its negotiation and adop-tion at the Diplomatic Conference held in Vienna, 14–17 June 1994,and the Final Act including an Annex entitled “Some clarificationwith respect to procedural and financial arrangements, nationalreports and the conduct of review meetings, envisaged in theConvention on Nuclear Safety’’.

Contents: Convention on Nuclear Safety; Decision adopted on21 February 1994 by the Board of Governors of the IAEA(GOV/2706); Resolution adopted by the General Conference at itsThirty-Seventh regular session (GC(XXXVII)RES/615);

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Diplomatic Conference convened to adopt the Convention onNuclear Safety; Final Act; Annex.

STI/PUB/962 (110 pp.; 1994)E ISBN 92–0–102294–8Price: 400 Austrian schillings (€29.07)

DEFINITION AND RECOMMENDATIONS FOR THECONVENTION ON THE PREVENTION OF MARINE POLLUTIONBY DUMPING OF WASTES AND OTHER MATTER, 1972–1986 Edition: A Safety GuideSafety Series No. 78


Contents: Scope; 1. Introduction to the Definition and Recommen-dations; 2. Definition of high level radioactive waste or other highlevel radioactive matter unsuitable for dumping at sea; 3. Recom-mendations required by Annex II of the Convention pertaining to thedumping of radioactive wastes; Annex I. Derivation of the quantita-tive definition of wastes unsuitable for dumping at sea; Annex II.Comparison with previous Definition and Recommendations;Annex III. Summary of meetings and documentation.







Proceedings of an international conference jointly organized by theEC, IAEA, Interpol and WCO and held in Dijon, France,14–18 September 1998. The conference was the first of its kinddevoted to this subject and brought together radiation safety experts,regulators, and customs and police officers, in order to foster infor-mation exchange through a review of the state of the art and opendiscussions. The need was expressed for the formulation of interna-tional recommendations concerned with the effective operation ofnational systems for ensuring the safety of radiation sources and thesecurity of radioactive materials. These proceedings contain thekeynote address, the invited papers, summaries of discussions andsession summaries. Together with IAEA-TECDOC-1045, publishedin 1998 prior to the conference, they constitute the complete recordof the conference.

Contents: Opening session; The problem; Response from interna-tional organizations; The regulatory control of radiation sources,including systems for notification, authorization (registration andlicensing) and inspection; Safety assessment techniques applied toradiation sources: Design and technological measures, includingdefence in depth and good engineering practice; Managerialmeasures, including safety culture, human factors, quality assur-ance, qualified experts, training and education; Learning from oper-ational experience; International co-operation, including reportingsystems and databases; Verification of compliance, monitoring ofcompliance: Assessment of the effectiveness of nationalprogrammes for the safety of sources, including development ofperformance indicators; Measures to prevent breaches in the secu-rity of radioactive materials (from production to disposal), experi-ence with criminal acts involving radioactive materials; Detectionand identification techniques for illicitly trafficked radioactive mate-rials (I and II); Response to detected cases and seized radioactivematerials, strengthening of the awareness, training, and exchange ofinformation; Summaries by chairpersons of the technical sessions.


L E G A L M A T T E R S

INTERNATIONAL NUCLEARINFORMATION SYS TEM

INIS DATABASE ON CD-ROM ➜NEWThe INIS Database on CD-ROM contains records from 1970 to thepresent and is updated quarterly. The full set consists of sevenarchival discs covering 1970 to 1996 and a current disc starting inJanuary 1997. A demo disc is available free of charge, containing thefirst quarter of 1997 INIS data (22,907 records), includingWINSPIRSTM and PC-SPIRSTM retrieval software, Quick ReferenceGuides and installation instructions.

Price: US$ 400 (approximately 5300 Austrian schillings (€385) for thecomplete set)US$ 200 (approximately 2600 Austrian schillings (€189) for anannual subscription to the current disc (four quarterly updates))

INIS NON-CONVENTIONAL LITERATURE (NCL) ➜NEWON CD-ROM

The INIS non-conventional literature (NCL) on CD-ROM containsthe full text of NCL beginnning with INIS Atomindex Vol. 28, No. 1(1 January 1997). New discs are added as needed and mailed on amonthly basis. A demo disc is available free of charge, containing445 separate items of literature in 183 reports (11,661 pp.).

Price: Yearly subscription: approximately 50 CD-ROMs/year charged at the rate of US$ 40/disc (approximately 500 Austrian schillings/(€36.34))Single disc: US$ 55 (approximately 700 Austrian schillings/(€50.87)) per CD-ROM

I N I S R E F E R E N C E S E R I E S

The INIS Reference Series defines the rules, standards, formats,codes and authority lists on which the International Nuclear Infor-mation System is based. Over the years most manuals have beenrevised or merged, and further revisions will be issued in the future.The series consists of 10 current manuals, all of which are availablein print, on microfiche and many in electronic form, as describedbelow.

INIS: GUIDE TO BIBLIOGRAPHIC DESCRIPTIONINIS Reference Series No. 1

This manual (formerly published under the title ‘Descriptive Cata-loguing Rules’) contains the rules, standards and formats for biblio-graphic descriptions adopted by centres preparing input to INIS. Therules are presented in a simplified style and several examples areprovided to clarify the texts. Various appendices are included,among them: the INIS character set; the INIS rules for entering

romanized Chinese personal names; a list of corporate abbrevia-tions; and a list of state and province codes for several countries.Also included in this current revision is the information contained inINIS: Terminology and Codes for Countries and International Orga-nizations (IAEA-INIS-5) and INIS: Transliteration Rules forSelected Non-Roman Characters (IAEA-INIS-10). This manual isintended to be used in conjunction with a companion volume enti-tled INIS: Descriptive Cataloguing Samples (IAEA-INIS-2).

IAEA-INIS-1 (Rev. 8) (198 pp., 21×30 cm; 1992)ISBN 92–0–104892–0Price: 520 Austrian schillings (€37.79)

INIS: SAMPLES FOR BIBLIOGRAPHIC ➜NEWDESCRIPTIONINIS Reference Series No. 2

This manual contains samples prepared in accordance with the latestINIS cataloguing rules as set out in IAEA-INIS-1 (Rev. 8): Guide toBibliographic Description and its updates. The samples contain allthe parts required for submitting records to INIS, i.e. the biblio-graphic and indexing parts as well as the abstract, but the commentsfocus on aspects of bibliographic description.

IAEA-INIS-2 (Rev. 7) (55 p., 21×30 cm; 1996)ISBN 92–0–103896–8Price: 120 Austrian schillings (€8.72)

INIS: SUBJECT CATEGORIES AND ➜NEWSCOPE DESCRIPTIONSINIS Reference Series No. 3

This manual serves two purposes: it defines the subject scope ofINIS as well as its subject classification scheme. The INIS subjectscope covers all aspects of the peaceful uses of nuclear science andtechnology. A redefinition of scope descriptions of categories hadbecome necessary (a) to better define categories dealing with basicscience, e.g. actual or potential nuclear applications or radiationeffects, and (b) to better reflect the IAEA’s new areas of interest. Thepresent revision also includes an updated version (1992) of the Inter-national Nuclear Event Scale (INES).


INIS: INSTRUCTIONS FOR SUBMITTING ABSTRACTSINIS Reference Series No. 4

This revision of IAEA-INIS-4 provides up-to-date rules on theformal submission of abstracts to INIS, as well as a guide to thetechniques of abstracting. It is meant not only for writers of abstractsbut also for those who may be guided by the abstract in selecting

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input and those whose critical assessment of what constitutes auseful, acceptable and informative abstract may give rise to feed-back to the document source. Thus the manual acts as a guide toprogressive improvement in the quality of accompanying abstracts.


INIS: SPECIFICATIONS FOR MACHINE READABLE DATA EXCHANGEINIS Reference Series No. 7

This manual combines the former IAEA-INIS-7 (Rev. 2), INIS:Character Set Representation and Coding Rules, with the obsoleteIAEA-INIS-8 (Rev. 1), INIS: Paper Tape Specifications and RecordFormat, and the obsolete IAEA-INIS-9 (Rev. 3), INIS: MagneticTape Specifications and Record Format. It contains the revised INIScharacter set and representations of it, together with encoding rulesfor the exchange format and, specifically for input, the worksheetformat on magnetic tape and diskette. It is divided into three parts:Part I: Character set and encoding rules; Part II: Worksheet formaton magnetic tape and diskette; Part III: Magnetic tape exchangeformat and specifications (corresponding to ISO Standard 2709).The INIS 8-bit code is an extension of the ISO Standard 646 physi-cal character set for information interchange. The document alsocontains instructions on how to encode symbols occurring in scien-tific and technical texts.


INIS: AUTHORITY LIST FOR JOURNAL TITLES ➜NEWINIS Reference Series No. 11

The twenty-fifth revision of this manual contains the names of12 249 journal titles covered by INIS. In Part I of the publication,journal titles are grouped by country or international organizationresponsible for their processing for INIS. Within the groups they areordered alphabetically by full journal title, followed by ISSN and/orCODEN if available, and any information concerning the status ofthe journal. In Part II the journals are arranged in alphabetical orderby full journal title, followed by ISSN and/or CODEN if available,and country in parentheses, and any information concerning thestatus of the journal. Journals marked with an asterisk are regularlyscanned for INIS. Journals with a number sign (#) are ‘KeyJournals’.


INIS: MANUAL FOR SUBJECT ANALYSIS ➜NEWINIS Reference Series No. 12

This manual covers the subject analysis part of input preparation,including document selection, subject classification, abstracting andsubject indexing. It presents the rules, guidelines and procedures tobe adopted by centres submitting input to the INIS Database. Themanual should be used in conjunction with the INIS Thesaurus(IAEA-INIS-13), the Subject Categories and Scope Descriptions(IAEA-INIS-3) and the Instructions for Submitting Abstracts(IAEA-INIS-4). It also constitutes part of the ETDE (Energy Tech-nology Data Exchange) Procedures Manual.


INIS: THESAURUS ➜NEWINIS Reference Series No. 13

The Thesaurus gives the controlled vocabulary to be used by INISmembers to index the literature they report to INIS. This authorityensures consistent subject indexing. Revision 38 contains 19 007accepted terms (descriptors) and 6676 forbidden terms (non-descriptors). The terms are listed alphabetically, and with each entrya ‘word block’ containing all the terms associated with that particu-lar entry is displayed. A revision of the Thesaurus is issued once ayear; cumulative updates are normally issued monthly.


THESAURUS del Sistema Internacional de Documentación Nuclear INIS (Versión española)INIS Reference Series No. 13/S

The Thesaurus gives the Spanish translation of the controlled vocab-ulary to be used by INIS members to index the literature they reportto INIS. This authority ensures consistent subject indexing. Revision32 of the Spanish version contains 19 422 accepted terms (descrip-tors) and 6065 forbidden terms (non-descriptors). The terms arelisted alphabetically in Spanish, followed by the English equivalent,and with each alphabetic entry a ‘word block’ containing all theterms associated with that particular entry is displayed.

IAEA-INIS-13/S (Rev. 32) (1032 pp., 21×30 cm; 1994)ISBN 92–0–300194–8Price: 1400 Austrian schillings (€101.74)

INIS: MULTILINGUAL DICTIONARYPart I: ENGLISH — FRENCH — GERMAN — RUSSIAN — SPANISHINIS Reference Series No. 20

INIS: DICTIONNAIRE MULTILINGUEPARTIE II: FRANÇAIS — ANGLAIS — ALLEMAND — RUSSE — ESPAGNOL

INIS: MEHRSPRACHIGES WÖRTERBUCHTEIL III: DEUTSCH — ENGLISCH — FRANZÖSISCH —RUSSISCH — SPANISCH

INIS: МНОГОЯЗЫЧНЫЙ СЛОВАРЬ ЧАСТЬ IV: РУССКИЙ —АНГЛИЙСКИЙ — ФРАНЦУЗСКИЙ — НЕМЕЦКИЙ

INIS: DICCIONARIO MULTILINGUEPARTE V: ESPAÑOL — INGLES — ALEMAN — FRANCES — RUSO

This publication, issued in five parts, contains the terminology of theINIS Thesaurus (IAEA-INIS-13) translated from English intoFrench, German, Russian and Spanish. Each of the five parts issorted alphabetically by the first-named language. The multilingualdictionary is intended as a tool to assist INIS users whose mothertongue is not English. It may also be useful to others in the nuclearfield such as translators, interpreters and authors who are confrontedwith specialized terminology in any of the five languages named.

IAEA-INIS-20 (Rev. 1) (E, F, G, R or S)Part I (585 pp., 21×30 cm; 1995)E out of printPart II (582 pp., 21×30 cm; 1995)F ISBN 92–0–202695–5Part III (553 pp, 21×30 cm; 1995)G ISBN 92–0–702795–X

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Part IV (561 pp., 21×30 cm; 1995)R ISBN 92–0–402895–0Part V (578 pp., 21×30 cm; 1995)S ISBN 92–0–302995–8Price per Part: 880 Austrian schillings (€63.95)

INIS: DATABASE MANUAL ➜NEWINIS Reference Series No. 22

This manual provides information for users of INIS output data onmagnetic media. It gives a description of each data element includ-ing information on contents, structure and usage, and a historicaloverview of additions, deletions and changes of data elements andtheir contents that have taken place over the years.

IAEA-INIS-22 (Rev. 1) (42 pp., 21×30 cm; 1997)ISBN 92–0–103297–8Price: 120 Austrian Schillings (€8.72)

INIS: FIBRE USER’S MANUALINIS Reference Series No. 23

This manual provides information and guidance on how to use theFIBRE (Friendly Inputting of Bibliographic Records) software atINIS input centres to prepare and submit records to be included inthe INIS database. The manual also provides information on how toinstall the software.

IAEA-INIS-23 (103 pp., 21×30 cm; 1995)ISBN 92–0–100295–5Price: 200 Austrian schillings (€14.53)

I N T E R N A T I O N A L N U C L E A R I N F O R M A T I O N S Y S T E M

ENVIRONMENT

APPLICATIONS OF ISOTOPES AND RADIATION IN CONSERVATION OF THE ENVIRONMENTProceedings Series

Proceedings of a symposium held in Karlsruhe, 9–13 March 1992.The objective was to review present knowledge of the applicationsof radiation, radioisotopes and nuclear methods of analysis in themonitoring and control of environmental pollution and in reducingemissions of environmentally toxic substances. Isotopes and radia-tion have many characteristics which uniquely contribute to thebetter understanding of environmental processes, as well as directlyprotect the environment from the impact of toxic substances. Thesekinds of applications form the focus of this volume.

Contents: Overviews of some main areas of application of nucleartechniques; Flue gas purification; Radiation processing of liquid andsolid wastes; Industrial applications; Radiotracer studies; Majoranalytical techniques and new approaches in environmental moni-toring and research; Nuclear analytical techniques and their applica-tions: 1. Atmospheric studies; 2. Studies of solid wastes, sedimentsand soils; 3. Hydrochemical and miscellaneous studies; Panel:Current problems and future trends in the use of isotopes and radia-tion for conservation of the environment.


ASSESSING THE IMPACT OF DEEP SEA DISPOSAL OF LOW LEVEL RADIOACTIVEWASTE ON LIVING MARINE RESOURCESTechnical Reports Series No. 288

In revising the Definition of high level radioactive waste unsuitablefor dumping at sea, calculations of water concentrations in and neara dump site have been made and used to estimate doses to ‘typical’marine species living at or near the sea floor at a depth of 4000 m.These calculations show that there are radionuclides that can giverise to significant doses to these typical species and that future revi-sions of the Definitions and Recommendations under the Conven-tion on the Prevention of Marine Pollution by Dumping of Wastesand Other Matters will have to consider impacts on the marineecosystem in setting limits for dumping.

Contents: 1. Introduction; 2. Nature of the deep sea ecosystem;3. Naturally occurring and fallout radionuclides in the marine envi-ronment; 4. Effects of radiation on aquatic organisms; 5. Methods ofdosimetry for aquatic organisms and an estimate of the backgrounddose rate in the deep sea; 6. Derivation of dose rates to organismsbased on the IAEA Definition of high level radioactive waste unsuit-able for dumping at sea; 7. Dose rates arising from actual seadumping operations; 8. Summary and conclusions; Appendix: Equa-tions and parameters used for calculations and results.


ATMOSPHERIC DISPERSION IN NUCLEAR POWER PLANT SITING: A Safety GuideSafety Series No. 50-SG-S3

The guide addresses the meteorological investigations needed atdifferent stages in a site survey, in site evaluation and in assessingoff-site consequences of operational states and accident conditions.It covers meteorological phenomena and mechanisms involved inthe dispersion of radioactive effluents, calculation methods forconcentration and deposition, input data needed for calculations,meteorological instrumentation requirements, data analysis systemrequirements and other related topics.

Contents: Introduction; On-site and off-site meteorological investi-gation programme; Atmospheric dispersion models; Averageshort-term concentration estimates; Meteorological aspects of emer-gency planning at nuclear power plants; Annex I: Turbulence andatmospheric dispersion; Annex II: Atmospheric stability; Annex III:Equivalent height of plume Dh (non-buoyant plume); Annex IV:Examples of simplified models; Annex V: A direct method for deter-mining stability class (Pasquill method and modifications); AnnexVI: Dependence of concentration on sampling time; Annex VII:Modified Bulk Richardson number method for sy and sz; AnnexVIII: Additional graphs for sy and sz.

STI/PUB/549 (107 pp., 16 figures; 1980)E ISBN 92–0–623180–4C ISBN 92–0–523886–4F out of printR out of printS ISBN 92–0–323382–2Price: 250 Austrian schillings (€18.17)

CONVENTION ON EARLY NOTIFICATION OF A NUCLEAR ACCIDENT AND CONVENTION ON ASSISTANCE IN THE CASE OF A NUCLEAR ACCIDENT OR RADIOLOGICAL EMERGENCYLegal Series No. 14

This publication contains the texts of the conventions as adopted andbackground material relating to the process of their negotiation andconclusion.

Contents: Convention on Early Notification of a Nuclear Accident;Convention on Assistance in the Case of a Nuclear Accident or Radi-ological Emergency.

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STI/PUB/765 (126 pp.; 1987)E ISBN 92–0–176087–6F ISBN 92–0–276088–8R ISBN 92–0–476090–7S ISBN 92–0–376089–XPrice: 340 Austrian schillings (€24.71)

DEFINITION AND RECOMMENDATIONS FOR THE CONVENTION ON THE PREVENTION OF MARINE POLLUTION BY DUMPING OF WASTES AND OTHER MATTER, 1972–1986 Edition: A Safety GuideSafety Series No. 78


Contents: Scope; 1. Introduction to the Definition and Recommen-dations; 2. Definition of high level radioactive waste or other highlevel radioactive matter unsuitable for dumping at sea; 3. Recom-mendations required by Annex II of the Convention pertaining to thedumping of radioactive wastes; Annex I. Derivation of the quantita-tive definition of wastes unsuitable for dumping at sea; Annex II.Comparison with previous Definition and Recommendations;Annex III. Summary of meetings and documentation.


EFFECTS OF IONIZING RADIATION ON PLANTS AND ANIMALS AT LEVELS IMPLIED BY CURRENT RADIATION PROTECTION STANDARDSTechnical Reports Series No. 332

Releases of waste gases and liquids into the environment from facil-ities using radioactive materials are controlled so that people livingin the vicinity are adequately protected from exposure to ionizingradiations. It is implicitly assumed that protecting humans will alsoprotect the environment in which they live. Although this assump-tion has never been formally defended, neither has it been seriouslychallenged. This report examines the validity of the assumption forthe case of radioactive releases to the terrestrial and freshwater envi-ronments and also for solid waste disposal underground.

Contents: 1. Introduction; 2. Summary of the available informationon the effects of ionizing radiation on populations; 3. Estimated doseto plants and animals under current radiation protection standards;4. Summary and conclusions; References.



Proceedings of a Senior Expert symposium jointly organized by theCommission of the European Communities, the Council for Mutual

Economic Assistance, the Economic Commission for Europe, theInternational Atomic Energy Agency, the International EnergyAgency, the International Institute for Applied Systems Analysis, theNuclear Energy Agency of the OECD, the United Nations Environ-ment Programme, the World Bank, the World Health Organizationand the World Meteorological Organization, in co-operation withthe Government of Finland, and held in Helsinki, Finland,13–17 May 1991. The objective of the symposium was to provide acomprehensive assessment of the environmental and health factorsas well as the economic factors involved in supplying electricityservices, and to suggest a framework within which these issuesshould be taken into account in making future plans and decisionson electricity production and use. The potential role of differentways of meeting electricity service requirements was also analysed,taking into consideration both demand side and supply options in thelight of their comparative economic, environmental and healthrelated impacts.

Contents: Opening session; Energy and electricity supply anddemand: Implications for the global environment; Energy sourcesand technologies for electricity generation; Comparative environ-mental and health effects of different energy systems for electricitygeneration; Incorporation of environmental and health impacts intopolicy, planning and decision making for the electricity sector;Luncheon sessions; Policy aspects of electricity and the environ-ment; Key issues and findings and round table on challenges forinternational co-operation.


ENVIRONMENTAL BEHAVOUR OF ➜NEWCROP PROTECTION CHEMICALSProceedings Series

Proceedings of a symposium on the Use of Nuclear and RelatedTechniques for Studying Environmental Behaviour of Crop Protec-tion Chemicals jointly organized by the IAEA and FAO, Vienna,1–5 July 1996. Use of pesticides has become an integral componentof agricultural systems worldwide. Concerning the environment,information must be provided before a product is registered in orderto provide assurance that it can be used without unacceptable hazardto non-target organisms. In addition, post-registration surveillanceand monitoring studies are necessary to check that the fate and envi-ronmental effects of pesticides under field conditions are consistentwith predictions. Much of the data are generated using radioisotopesand other nuclear or related methods. Developing countries oftenhave to rely on data generated elsewhere in order to assess theacceptability of a compound. The purpose of the symposium was toexamine the circumstances under which extrapolation from oneenvironment to another is valid on the basis of data generated undercomparable conditions. It also considered ways in which relativelysimple methods can be used to verify the field applicability of dataobtained under sophisticated experimental conditions.

Contents: Opening session; Pesticides in the environment: Interna-tional perspective; Pesticides in the environment: Regional andcountry situations; Fate and behaviour of pesticides in the terrestrialenvironment; Fate and behaviour of pesticides in the aquaticenvironment; Comparison of fate and behaviour of pesticides indifferent environments; Effect of pesticides on non-target species;Maximizing the use of environmental data.


E N V I R O N M E N T

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ENVIRONMENTAL CONTAMINATION FOLLOWING A MAJOR NUCLEAR ACCIDENTProceedings Series

Proceedings of a symposium jointly organized with the Food andAgriculture Organization of the United Nations, the United NationsEnvironment Programme and the World Health Organization,Vienna, 16–20 October 1989. The extent and effects of the potentialcontamination due to a major accident at a nuclear facility arematters of public concern. Scientific research on the after-effects ofthe Chernobyl accident on the environment and on human health hasprovided new data pertaining to large scale contamination. Papers atthe symposium covered a wide range of subjects, including: moni-toring of radioactive contaminants in the environment, levels ofradioactive contamination of farmland, agricultural crops and dairyproducts in subsequent years, methods for minimizing contamina-tion of feed and food.

Contents: Vol. 1: Part I: Radioactive contamination of the environ-ment: (a) General; (b) Air; (c) Soil; (d) Water; Part II: Monitoring ofradioactivity: (a) General; (b) Strategies and policy; (c) Methods andtechniques. Vol. 2: Part III: Radioactive contamination of agricul-tural land and agricultural produce; Part IV: Countermeasures toreduce radionuclide contamination of food chains; Part V: Radiationexposure of populations; Part VI: Radionuclides and internationaltrade in food; Special Session: Hot particles; Summary of theSymposium: Important Issues with Significance for the Future.



ENVIRONMENTAL IMPACT OFRADIOACTIVE RELEASESProceedings Series

Proceedings of a symposium, Vienna, 8–12 May 1995. This was thefirst major IAEA meeting for more than a decade to deal specificallywith the transfer of radionuclides in the environment. Its purposewas to review the information that has become available in recentyears, notably as a result of the Chernobyl accident but also gainedfrom studies of the discharges from civil and military nuclear facil-ities in the early nuclear age. This information has been used forimproving the reliability of environmental model predictions, andthe main results of the IAEA/CEC programme on Validation ofEnvironmental Model Predictions (VAMP) were presented. In addi-tion, progress in the IAEA programme on the International ArcticSeas Assessment Project (IASAP) was summarized.

Contents: Global impact assessments; New roles for environmentalmonitoring; Radionuclide releases to the atmosphere; Radionuclidereleases to the aquatic environment; Radionuclides in the terrestrialenvironment; Radionuclide transfer in the freshwater environment;Environmental model testing; Radiological impact assessment;Environmental remediation; Topical discussions.


E N V I R O N M E N T A L I S O T O P E D A T A : W O R L D S U R V E Y O F I S O T O P E C O N C E N T R A T I O N I N P R E C I P I T A T I O N

is a series of Technical Reports, the first of which was published in1969, containing data collected by the IAEA/WMO Isotopes-in-

Precipitation Network of national laboratories set up by the IAEA inco-operation with the World Meteorological Organization in 1953.

ENVIRONMENTAL ISOTOPE DATA No. 8:WORLD SURVEY OF ISOTOPE CONCENTRATION IN PRECIPITATION (1980–1983)Technical Reports Series No. 264

Contents: Introduction; Data printouts (late reports, notes); Numer-ical station index; Alphabetical station index; Appendix 1: Codenumbers for tritium laboratories; Appendix 2: Code numbers fordeuterium and oxygen-18 laboratories.


ENVIRONMENTAL ISOTOPE DATA No. 9:WORLD SURVEY OF ISOTOPE CONCENTRATION IN PRECIPITATION (1984–1987)Technical Reports Series No. 311

Contents: Introduction; Data printouts; Numerical station index;Alphabetical station index; Appendix 1: Tritium laboratory codenumbers; Appendix 2: Deuterium and oxygen-18 laboratory codenumbers.


ENVIRONMENTAL ISOTOPE DATA No. 10: WORLD SURVEY OF ISOTOPE CONCENTRATIONIN PRECIPITATION (1988–1991)Technical Reports Series No. 371

This is the tenth and latest volume in the present series. It is mainlyconcerned with the concentration of the environmental isotopes(tritium, deuterium and oxygen-18) in monthly samples of precipi-tation taken by a global network of 169 stations in the period1988–1991. Selected meteorological data, such as the amount ofprecipitation, mean water vapour pressure and surface air tempera-ture, are also presented. Data before 1988 which were unavailable atthe time of the earlier issues have also been included in the latter partof this volume as late reports. The great majority of the data comesfrom the IAEA/WMO Isotopes-in-Precipitation Network, whichwas set up by the IAEA in co-operation with WMO and sevennational laboratories. The collection of the precipitation samples iscarried out by the meteorological services in 45 countries and terri-tories. Analyses of the network samples are made in co-operatinglaboratories, a full list of which is given at the end of thispublication.

Contents: Introduction; Data printouts; Numerical station index;Alphabetical station index; Appendix 1: Laboratories which haveco-operated or are co-operating in the IAEA/WMO network;Tritium laboratories; Stable isotopes laboratories.



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EVALUATING THE RELIABILITY OF PREDICTIONS MADE USING ENVIRONMENTAL TRANSFER MODELS: A Safety PracticeSafety Series No. 100

This publication provides guidance on the available methods forevaluating the reliability of environmental transfer modelpredictions. It provides a practical introduction to the subject, andparticular emphasis has been given to worked examples in the text.It is intended to supplement existing IAEA publications on environ-mental assessment methodology. Although the book addresses thesubject of environmental dose assessment, the methods describedare of general application and are equally useful in other areas wheremodelling techniques are applied.

Contents: 1. Introduction; 2. General aspects of model reliabilityevaluation; 3. Practical approaches to the evaluation of model relia-bility; Appendix I: Statistical equations; Appendix II: Latin hyper-cube sampling; Appendix III: Examples of parameter uncertaintyanalyses; Glossary.


GUIDELINES FOR AGRICULTURAL COUNTERMEASURES FOLLOWING AN ACCIDENTAL RELEASE OF RADIONUCLIDESTechnical Reports Series No. 363

This report is a collation of information and experience gained fromthe Chernobyl accident in 1986 concerning the transfer of radionu-clides, especially 137Cs and 90Sr, through food chains to humans andthe ways to effectively reduce them. Accounts of measures taken invarious countries following the Chernobyl accident, which at thetime caused significant radioactive contamination of the environ-ment over widely separated areas, some relatively remote from thesite, are included.

Contents: Part I. Introduction; 1. Introduction; 2. General con-siderations; 3. Developing a strategy for agricultural counter-measures; Part II. Agricultural countermeasures: Scientific basis andpractice; 4. Introduction; 5. Preventive measures to be appliedbefore and during the arrival of radioactive fallout; 6. Counter-measures to be applied in the first few weeks after deposition;7. Countermeasures to be applied in the medium and long term;8. Losses of radionuclides in food by processing and culinary prepa-ration; Part III. Organizing for response; 9. Introduction; 10. Emer-gency preparedness; 11. Response; 12. Public information andinformation for farmers; Part IV. Contamination in agriculture frompast nuclear accidents; 13. Introduction; 14. Nuclear accidentrequiring countermeasures only in the short term; 15. Nuclear acci-dent requiring countermeasures in both the short and long term;Glossary.


HANDBOOK OF PARAMETER VALUES FOR THE PREDICTION OF RADIONUCLIDE TRANSFER IN TEMPERATE ENVIRONMENTSTechnical Reports Series No. 364

This handbook has been produced in collaboration with the Interna-tional Union of Radioecologists. It should serve as a convenient andauthoritative reference for radionuclide transfer parameter valuesused in biospheric assessment models. It supplements Safety Series

No. 57 (1982), ‘‘Generic Models and Parameters for Assessing theEnvironmental Transfer of Radio- nuclides from Routine Releases’’.

Contents: 1. Introduction; 2. Agricultural systems — vegetation;3. Agricultural systems — milk, meat and eggs; 4. Freshwaterecosystems — fish; 5. Natural ecosystems; 6. Food processing trans-fer parameters.



Proceedings of a symposium held in Hyderabad, India, 4–7 Novem-ber 1996. The aim of the symposium was to provide an internationalforum for discussion of the applications of nuclear analytical tech-niques and related isotopic tracer methods, particularly in the area ofanalytical quality assurance, including validation of analyticalmethods and development of new analytical reference materials. Asthese methodologies contribute substantially to the harmonization ofdata, they are playing an important role in the application of newlyemerging techniques such as quality management and quality assur-ance standards (e.g. ISO-25 and ISO-9000) in environmental analyt-ical laboratories. The symposium programme covered a wide varietyof applications of nuclear (and related) analytical techniques(mainly neutron activation analysis, energy dispersive X ray fluo-rescence, particle induced X ray emission and inductively coupledplasma-mass spectrometry) as used in the study of air particulates,solid waste products, sediments, food, water, human tissues,biomonitors and other kinds of environmental samples.

Contents: Quality systems and strategies; Reference materials:Production, certification and use; Nuclear analytical techniques:General aspects and quality assurance/quality control; Nucleartechniques and applications of quality assurance/quality control:Biological systems; Nuclear techniques and applications of qualityassurance/quality control: Non-biological systems; Posterpresentations.


HEALTH AND ENVIRONMENTAL IMPACTS OF ➜NEWELECTRICITY GENERATION SYSTEMS:PROCEDURES FORCOMPARATIVE ASSESSMENTTechnical Reports Series No. 394

The present report is intended to assist in the design and implemen-tation of comparative risk assessment studies for the estimation ofhealth and environmental impacts of various electricity generationoptions. It sets out the framework for carrying out such assessmentsand identifies the major technical issues and uncertainties in theassessment process.

Contents: 1. Introduction; 2. Impacts and impact assessment: Basicconcepts; 3. Methodological approach for estimating health andenvironmental impacts; 4. Calculation and use of impact indicatorsfor comparative assessment; 5. Key methodological issues; Appen-dix I: Global climate change; Appendix II: Energy security.



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HYDROLOGICAL DISPERSION OF RADIOACTIVE MATERIAL IN RELATION TO NUCLEAR POWER PLANT SITING: A Safety GuideSafety Series No. 50-SG-S6

This guide deals with the dispersion of normal and accidentalreleases of radioactive material from nuclear power plants intosurface water for a full range of releases, including steady state(routine releases), instantaneous or puff (accidental releases), andtime dependent long term releases (routine or accidental releases). Itdescribes the Information needed and gives recommendations onmeasurement programmes and on the selection and use of appropri-ate mathematical models for evaluating dispersion.

Contents: Introduction; Information needed at the site survey stage;Information needed at the site evaluation stage; Modelling ofradionuclide dispersion in surface waters; Appendix A: Generaldiscussion of radionuclide dispersion modelling in surface waters;Appendix B: Models for the initial dilution of radioactive material;Appendix C: Models for far-field radionuclide dispersion in rivers;Appendix D: Models for far-field radionuclide dispersion from opencoasts; Appendix E: Models for dispersion of radionuclides in estu-aries; Appendix F: Models for far-field radionuclide dispersion inimpoundments; Annex I: Measurement of diffusion coefficients;Annex II: Measurement of equilibrium sediment distribution coeffi-cients; Annex III: Examples of accuracy and sensitivity of instru-mentation; Annex IV: Equations of simple models for radionuclidedispersion in rivers, open coasts, estuaries and impoundments;Annex V: Advanced models for radionuclide dispersion in rivers;Annex VI: Advanced models for radionuclide dispersion in the nearshore of open coastal areas; Annex VII: Advanced models for radio-nuclide dispersion in estuaries; Annex VIII: Advanced models forradionuclide dispersion in impoundments; Annex IX: Depositedairborne radioactive material as a source for dispersion in surfacewaters.

STI/PUB/539 (116 pp., 14 figures; 1985)E ISBN 92–0–123285–3F ISBN 92–0–223889–8R ISBN 92–0–423587–XS ISBN 92–0–323187–0Price: 360 Austrian schillings (€26.16)

ISOTOPE TECHNIQUES IN THE ➜NEWSTUDY OF ENVIRONMENTAL CHANGEProceedings Series

Proceedings of a symposium on Isotope Techniques in the Study ofPast and Current Environmental Changes in the Hydrosphere andthe Atmosphere, Vienna, 14–18 April 1998. The symposium wasstructured in five sessions of oral presentations, a poster session anda round table discussion that focused on trends and future require-ments in isotope hydrology and on applications in climate and envi-ronmental research. The major themes covered by the presentationsincluded the use of isotopic tracers in studies of atmospheric andhydrospheric changes and of human impacts on water and the envi-ronment. Special emphasis was placed on isotopic archives ofclimatic and environmental change. Some contributions addressednew technical approaches.

Contents: Opening session; Isotopic tracers of the atmosphere;Isotopic tracers of the hydrosphere; Isotopic studies of man-madehydrological impact; Isotopic archives of climatic and environmen-tal change; New technical approaches; Poster session.


ISOTOPE TECHNIQUES IN THE STUDY OF PAST AND CURRENT ENVIRONMENTAL CHANGES IN THE HYDROSPHERE AND THE ATMOSPHEREProceedings Series

Proceedings of a symposium held in Vienna, 19–23 April 1993.Natural isotopes are among the most powerful tools for investigat-ing past and current environmental changes. In particular, stableisotopes have proved to be very useful proxy indicators of climaterelated parameters such as surface air temperature, relative humidityof the atmosphere and amount of precipitation, whereas radioactiveisotopes are widely used as a dating tool. The release of radionu-clides during the nuclear bomb tests permitted studies of the dynam-ics of transport and mixing processes in the atmosphere. It alsoallowed a global tracer experiment on the hydrological and carboncycles, which substantially contributed to better understanding ofthese two vital compartments of the global ecosystem. A wide spec-trum of themes was discussed at the symposium, covering both the‘present’ and the ‘past’ of the global atmosphere/hydrospheresystem. Case studies as well as methodological aspects of variousisotope techniques applied in both areas of research were presented.

Contents: Isotopes in atmospheric studies; Isotopes in thesoil–plants–atmosphere system; Degradation of water resources;Palaeohydrology and palaeowaters; Isotope indicators of climaticchanges; Poster presentations.


ISOTOPE TECHNIQUES IN WATER RESOURCES DEVELOPMENTProceedings Series

Proceedings of a symposium organized in co-operation withUNESCO and held in Vienna, 30 March to 3 April 1987. Nucleartechniques using isotopes are precise tools for studying waterresources. They can provide solutions to the problem of the origin,distribution and properties of water in a given region, especiallywhen they are used in combination with other tools. The contents ofthese proceedings illustrate the fact that isotope hydrology hasbecome mature. It is reported that the development of new nucleartechniques is enabling the application of isotopes other than thoseused so far in hydrology.

Contents: Thermal water studies; Groundwater dating; Hydrologyof arid and semi-arid areas; Field studies with environmentalisotopes; Precipitation surface groundwater relationships; Pollution;Artificial tracers; Sediment transport; Poster presentations.


ISOTOPE TECHNIQUES IN WATER RESOURCES DEVELOPMENT 1991Proceedings Series

Proceedings of a symposium organized in co-operation withUNESCO and held in Vienna, 11–15 March 1991. The main themeswere the use of isotope techniques in solving practical problems ofwater resources assessment and development, particularly withrespect to groundwater protection, and in studying environmentalproblems related to water, including the palaeohydrological andpalaeoclimatological aspects. The oral presentations were largelyconcerned with the current status and trends in groundwater dating.The proceedings contain the papers of 37 oral presentations and theextended synopses of 47 poster presentations.


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Contents: Interface processes between the atmosphere and thehydrosphere; Surface water and sediments; Groundwater dating:Problems and new approaches; Groundwater dating: Problems andnew approaches — methodological aspects and models; Groundwa-ter; Environmental problems and water pollution; Palaeohydrologyand palaeoclimatology; Poster presentations.


ISOTOPES IN WATER RESOURCES ➜NEWMANAGEMENTProceedings Series

Proceedings of a symposium organized in co-operation withUNESCO and held in Vienna, 20–24 March 1995. The main topicsaddressed were water resources management, with emphasis onorigin and recharge of groundwater, groundwater dynamics andpollution, modelling approaches and geothermal and palaeowaterresources. The remaining discussions were concerned with surfacewater and sediments, unsaturated zones and methodological aspects.The proceedings contain the papers of 43 oral presentations and theextended synopses of over 100 poster presentations.

Contents: (Vol. 1) Recent developments; Surface water andsediments; Unsaturated zones; Origin and recharge of groundwater;(Vol. 2) Dynamics of groundwater; Groundwater pollution; Model-ling approaches; Geothermal and palaeowaters.



LABORATORY TRAINING MANUAL ON THE USEOF NUCLEAR AND ASSOCIATED TECHNIQUESIN PESTICIDE RESIDUESTechnical Reports Series No. 329

The present revised Manual gives a concise yet comprehensivepresentation of the basic principles necessary for the proper use ofnuclear and associated techniques in pesticide residue analysis toobtain information on the metabolism or fate of pesticide chemicalsin plants, animals, soil, water and non-target organisms.

Contents: Part I. Properties of radionuclides and radiation; Part II.Radiation detection and measurement of radioactivity; Part III.Radiation protection; Part IV. Tracer methodology; Part V. Radiationbiology; Part VI. Introduction to practical work; Part VII. Labora-tory exercises; Part VIII. Appendices; Part IX. Glossary.




Contents: 1. Introduction; 2. Pathways and samples of interest;3. Radionuclides of interest; 4. Requirements for laboratories,equipment and personnel; 5. Collection and preparation of samples;

6. Analytical methods; 7. Analytical quality control; References:Sections 1–7; Bibliography: Sections 1–7; Annex I: Method fordetermining gamma emitters; Annex II: Methods for radiochemicalanalysis of strontium; Annex III: Method for radiochemical analysisof tritium; Annex IV: Methods for radiochemical analysis of pluto-nium, americium and curium; Annex V: Units, prefixes and symbols;Annex VI: Nuclear accident scenarios; Annex VII: Radionuclidedata; Annex VIII: Grass sample collection; Annex IX: Gamma spec-trometric systems; Annex X: Potential suppliers of calibrationsources and reference materials.


NUCLEAR POWER PLANT SITING: HYDROGEOLOGICAL ASPECTS: A Safety GuideSafety Series No. 50-SG-S7

This guide deals with the determination of the radionuclideconcentration in groundwater resulting from postulated releasesfrom nuclear power plants. The main emphasis is on the behaviourof radioactive material in groundwater and on the methods forassessing the radionuclide movement in various aquifers. Thismovement of radionuclides in the ground is essentially controlled bythe phenomena of transport (bulk motion of ground water), hydro-dynamic dispersion (spread of contaminate front) and ion exchange.

Contents: Introduction; Site survey stage; Site evaluation stage;Modelling of radionuclide dispersion and retention in groundwater;Groundwater monitoring programme; Appendix A: Modelling ofradionuclide movement in groundwater; Annex I. Considerationsrelated to groundwater availability; Annex II. Analytical solutions ofthe advective transport and hydrodynamic dispersion equations;Annex III. Accuracy and reliability of measurements in hydrogeol-ogy; Annex IV. Examples of methods and frequencies of measure-ments within the monitoring programme; Special definitions.


NUCLEAR TECHNIQUES IN SOIL–PLANTSTUDIES FOR SUSTAINABLE AGRICULTURE AND ENVIRONMENTAL PRESERVATIONProceedings Series

Proceedings of a symposium jointly organized by the IAEA andFAO, Vienna, 17–21 October 1994. The objective of the symposiumwas to assess the progress being made in the use of nuclear andrelated techniques for studying various aspects of soil fertility andplant nutrition, environmental problems, the potential and limita-tions of existing methods, and the possibilities for further develop-ment. Analytical methods and equipment are discussed, as areisotope dilution techniques, transfers of fixed N to non-fixing crops,crop water consumption, labelled fertilizer involving fertigation, 13Cdiscrimination, erosion and soil degradation, and global warmingand climate change. The proceedings should assist scientists, partic-ularly those in developing countries, to find ways of increasing andsustaining soil fertility and crop production while preserving theenvironment.

Contents: Opening session; Recent developments in analyticalmethods and equipment; Fertilizer use and management studies;Biological nitrogen fixation in sustainable cropping systems; Soilorganic matter studies and nutrient cycling; Water use and manage-ment studies; Plant physiological aspects in crop production;


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Environmental pollution and preservation; Soil conservation, soilerosion and desertification; Poster session.


PRINCIPLES FOR LIMITING RELEASES OF RADIOACTIVE EFFLUENTS INTO THE ENVIRONMENT: A Safety GuideSafety Series No. 77

This publication is a complete revision of Safety Series No. 45, Prin-ciples for Establishing Limits for the Release of Radioactive Mate-rials into the Environment (1978), and its Annex (1982). It isconcerned with the subject of limiting releases of radioactive efflu-ents during normal, controlled operations of nuclear installations. Itdoes not deal with releases during accidents where it is only possi-ble to limit exposures by intervention. In practice, a choice must bemade between releasing radioactive materials directly from aninstallation, storing them, treating and disposing of them by somemeans, or a combination of these methods.

Contents: Concepts and quantities; Assessment of individual dose;Assessment of collective dose; Setting release limits; References;Explanation of terms.

STI/PUB/728 (32 pp., 3 figures; 1986)E out of printC ISBN 92–0–523690–XF ISBN 92–0–223587–2R ISBN 92–0–423089–4S ISBN 92–0–323387–3Price: 150 Austrian schillings (€10.90)

QUANTIFICATION, NATURE AND BIOAVAILABILITY OF BOUND 14C-PESTICIDE RESIDUES IN SOIL, PLANTS AND FOODPanel Proceedings Series

The publication contains the papers presented at a research co-ordination meeting held in Gainesville, Florida, 25–29 March 1985.The joint FAO/IAEA programme was designed to assist scientists ofdeveloping countries to make safe and effective use of nuclear tech-niques for studying pesticide interactions with various componentsof the agricultural ecosystems. The book also contains a report onthe results of a collaborative study using a model protocol for thedetermination of bound residues in soil and appraisal of the overallprogramme accomplishments.

Contents: Papers presented by the authors; FAO/IAEA modelprotocol for the determination of bound residues in soil; Final reporton the common experiment; Appraisal of the co-ordinated researchprogramme.


R A D I O L O G I C A L A S S E S S M E N T R E P O R T S S E R I E S

This series comprises reports on assessments made by the IAEA inareas around the world that are contaminated by radioactive residuesfrom past activities conducted without applying international radia-tion protection standards. Such residues result from peaceful activi-ties such as uranium mining and milling as well as from militaryactivities that were outside the scope of international standards,including the production and testing of nuclear weapons.

RADIOLOGICAL CONDITIONS AT ➜NEWBIKINI ATOLL: PROSPECTS FOR RESETTLEMENTRadiological Assessment Reports Series

The general concern about the state of the environment has focusedthe attention of many countries in recent years on the need to reme-diate areas affected by radioactive residues. The present assessmentwas requested by the Government of the Republic of the MarshallIslands, with the purpose of obtaining an independent view of theradiological situation on Bikini Atoll, the site of nuclear weaponstesting in the period 1946–1958. In particular, questions were posedabout whether the former inhabitants should be permitted to returnto their homes and about the nature and extent of any remedialactions which might be necessary. This report presents the resultsand conclusions of a meeting of international experts convened bythe IAEA and chaired by K. Lokan, Australia, in December 1995 toreview the available information on the subject.

Contents: 1. Summary; 2. The Marshall Islands; 3. Background:Nuclear weapon testing in the Marshall Islands and its aftermath atBikini Atoll; 4. The international review; 5. Radiological concepts inthe context of nuclear weapon testing; 6. Present environmentalradiological conditions at Bikini Atoll; 7. Estimates of potentialradiation doses to people resettling Bikini island under presentconditions; 8. Radiation protection criteria; 9. Habitability of Bikiniislands; 10. Conclusions and recommendations; References; Adden-dum: IAEA corroboratory monitoring mission to Bikini island.


RADIOLOGICAL CONDITIONS AT THE ➜NEWSEMIPALATINSK TEST SITE, KAZAKHSTAN: Preliminary Assessment and Recommendations for Further StudiesRadiological Assessment Reports Series

This report presents the findings of a study of the current radio-logical conditions at the former nuclear test site at Semipalatinsk,Kazakhstan, conducted by a team of international experts under theauspices of the IAEA at the request of the Government of Kaza-khstan. The objectives of the study were to assess the current andpotential future radiation doses to the residents of the Semipalatinsknuclear test site area and adjacent settlements, to advise on remedialaction, where appropriate, and to recommend whether further radio-logical evaluation of the area is warranted.

Contents: 1. Summary; 2. The Semipalatinsk test site; 3. Back-ground; 4. Programme of IAEA assistance; 5. Perspective on globalnuclear weapons testing; 6. Radiological conditions at the Semi-palatinsk test site; 7. Estimates of present and future doses topersons in and around the test site; 8. Radiation protection criteria;9. Conclusions and recommendations; Appendix: Method of assess-ing radiation doses.



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RADIOLOGICAL CONDITIONS OF ➜NEWTHE WESTERN KARA SEARadiological Assessment Reports Series

This report presents the findings of the International Arctic SeasAssessment Project (IASAP), which was designed to addressconcerns over the potential health and environmental impacts ofhigh level radioactive waste dumped in the shallow waters of theArctic Seas. The following aspects were covered: (i) examination ofthe current radiological situation in Arctic waters due to the dumpedwastes; (ii) evaluation of potential future releases from the dumpedwastes; (iii) prediction of environmental transport of potentialreleases and assessment of the associated radiological impact onhumans and biota; and (iv) examination of the feasibility, costs andbenefits of possible remedial measures.

Contents: Executive summary; 1. Introduction; 2. Radiologicalprotection and decision making; 3. The Arctic environment; 4. Theradioactive source term; 5. Environmental modelling for radiologi-cal impact assessment; 6. Possible remedial actions; 7. Analysis ofthe need for remedial actions; 8. Conclusions and recommendations.


THE RADIOLOGICAL SITUATION AT THE ATOLLS OF MURUROA AND FANGATAUFA Reports by an International Advisory CommitteeRadiological Assessment Reports Series

The Study of the Radiological Situation at the Atolls of Mururoa andFangataufa was conducted at the request of the Government ofFrance to determine whether, as a consequence of French nucleartests conducted above and beneath these atolls, radiological hazardscould arise, now or in the future; and to recommend the form, scaleand duration of any monitoring, remedial action or follow-up actionthat might be required. An International Advisory Committee wasconvened by the Director General of the IAEA to provide scientificdirection and guidance on the conduct of the Study. The firstmeeting of the IAC was held in April 1996 and its final meeting inFebruary 1998. In addition to IAEA Secretariat staff, 55 scientistsfrom 18 countries and four international organizations participatedin the Study, including the environmental sampling and surveillancecampaigns, which involved 18 laboratories in 12 countries.

The results of the Study are presented in four separate publications:The Main Report; the Executive Summary (which is also incorpo-rated in the Main Report); the Summary Report; and the TechnicalReport. The Main Report is the primary publication of the Study andprovides a comprehensive scientific account, together with findings,conclusions and recommendation. The Executive Summary is repro-duced from the original document presented to the IAEA Board ofGovernors. The Summary Report provides an extended synopsis ofthe Study for the benefit of a wider audience, and includes its find-ings, conclusions and recommendation in full. The Main Report issupported by the detailed Technical Report in six volumes, which isintended for the scientific specialist.

An international Conference was held from 29 June to 3 July 1998to present the Study to the scientific community. The proceedingscan be obtained with the Technical Report.

The Executive Summary and the Summary Report are availableseparately as priced publications. Purchasers of the Main Report(which incorporates the Executive Summary) will also receive theSummary Report at no extra cost, and may obtain the Technical

Report in six volumes and the Conference proceedings at no extracharge by returning the reply card included with the Main Report.

THE RADIOLOGICAL SITUATION ➜NEWAT THE ATOLLS OF MURUROA AND FANGATAUFA: Executive SummaryReport by an International Advisory CommitteeRadiological Assessment Reports Series

SITUATION RADIOLOGIQUE SUR LES ATOLLS DE MURUROA ET DE FANGATAUFA: SynthèseRapport par un Comité consultatif internationalCollection Rapports d’évaluations radiologiques

The Executive Summary, which is incorporated in the Main Reportand also available separately, presents a synopsis of the Main Reportfor the benefit of persons with executive, managerial or administra-tive responsibilities, together with its findings, conclusions andrecommendation. It is issued as one single publication in Englishand French.

Contents/Table des matières: Introduction/Introduction; Objec-tive/Objectif; Framework/Cadre; Conduct of the Study/ Conduite del’étude; Reports resulting from the Study/Rapports résultant del’étude; Findings/Résultats; Conclusions/Conclusions; Recommen-dation/Recommandation; Participants in the Study/Personnes ayantparticipé à l’étude.

STI/PUB/1028/ES (26 pp., 21 × 30 cm; 1998)ISBN 92–0–001898–XPrice: 200 Austrian schillings (€14.53)

THE RADIOLOGICAL SITUATION ➜NEWAT THE ATOLLS OF MURUROA AND FANGATAUFA: Main ReportReport by an International Advisory CommitteeRadiological Assessment Reports Series

The Main Report, which incorporates the bilingual (English/French) Executive Summary (see above), gives a comprehensivescientific account of the Study, together with data on the Frenchnuclear weapon tests. It presents the results of the Study’s assess-ment of the environmental legacy of weapon testing at the atolls andestimates of consequent radiation doses at present and in the future,drawing on the supporting detailed Technical Report. The findings,conclusions and recommendation are presented, together with anaccount of their basis in radiation protection and further backgroundmaterial to provide perspective.

Contents: Executive Summary; Part A: Background: 1. The Study;2. Geography, geology and history of the atolls; 3. Nuclear testingprogramme; Part B: Present and predicted radiological situations:4. Inventory of residual radioactive material in the biosphere at theatolls; 5. Inventory of residual radioactive material in the geosphereof the atolls; 6. Transport of residual radioactive material throughthe geosphere; 7. Effects of hypothetical disruptive events; 8. Trans-port of residual radioactive material through the marine environ-ment; Part C: Results I; 9. Radiation doses and their potential forimpact on human health; 10. Potential impact of radiation doses onbiota; 11. The need for remediation; Perspective; Part D: Conclu-sions and recommendations; 12. Findings; 13. Conclusions;14. Recommendation; References; Annex I: Retrospective assess-ment of the radiation doses attributable to atmospheric testing at theatolls; Annex II: Ciguatera: Incidence and cause; Annex III: Ioniz-ing radiation: Levels and biological effects; Annex IV: Some fissionand fusion physics and the testing of nuclear weapons; Glossary.


130

Purchasers of the Main Report will automatically receive theSummary Report at no extra cost.


THE RADIOLOGICAL SITUATION ➜NEWAT THE ATOLLS OF MURUROA AND FANGATAUFA: Summary ReportReport by an International Advisory CommitteeRadiological Assessment Reports Series

The Summary Report provides a synopsis of the Study for thebenefit of a wider audience, and includes its findings, conclusionsand recommendation in full. It explains the background to the Study,giving data on the French nuclear weapon tests, and summarizes theStudy’s assessment of the environmental legacy of weapon testing atthe two atolls. The Study’s estimates of consequent radiation dosesat present and in the future are summarized. The basis in radiationprotection for the Study’s conclusions and recommendation ispresented in brief. Additional material to aid understanding andprovide perspective is included in 14 text boxes.

Contents: Introduction; The nuclear weapon tests conducted byFrance in the South Pacific; The Study and the International Advi-sory Committee; Assessment of present radiological conditions;Assessment of future radiological conditions; Estimated doses dueto residual radioactive material; Conclusions and recommendation;Annex: French nuclear tests at the atolls of Mururoa and Fangataufa.


STABLE ISOTOPES IN PLANT NUTRITION, SOIL FERTILITY AND ENVIRONMENTAL STUDIESProceedings Series

Proceedings of a symposium jointly organized with the Foodand Agriculture Organization of the United Nations, Vienna,1–5 October 1990. The objective of the symposium was to evaluateprogress in the use of stable isotopes to examine various aspects ofsoil fertility and plant nutrition and some environmental problems,the potential and limitations of existing methods, and possibilitiesfor further development. The meeting focused on the site level ratherthan the landscape level and, more specifically, on soil–plantrelations, although landscape environmental aspects were alsoexamined. The underlying theme was an assessment of current andpossible future approaches to two problems of concern: how toincrease or sustain productivity with minimum inputs, and how tolimit environmental damage due to inappropriate land managementand to industry.

Contents: New methodologies and approaches in stable isotopeanalysis; Measurement of biological nitrogen fixation using 15Nadditions; the 15N natural abundance method for measurement ofbiological nitrogen fixation; Review of papers in Sessions 2 and 3;Applications of 15N methods to measurement of biological nitrogenfixation; Stable isotopes in soil organic matter studies; Soil nitrogentransformations and losses; Nutrient uptake and use by the plant;

Stable isotopes in studies of plant metabolism; 13C/12C discrimina-tion as a measure of water use efficiency; 13C in studies of plantcarbon balance; Stable isotopes in water transport studies; Sulphurflows and transformations in ecosystems; Atmospheric change andaerial pollutants.


STATISTICAL TREATMENT OF DATA ON ENVIRONMENTAL ISOTOPES IN PRECIPITATIONTechnical Reports Series No. 331

This publication is an extended and revised version of TechnicalReports Series No. 206, Statistical Treatment of EnvironmentalIsotope Data in Precipitation, published in 1981. It contains astatistical evaluation of isotope and meteorological data accumu-lated during three decades of operation of the global network,Isotopes in Precipitation, jointly operated by the IAEA and theWorld Meteorological Organization. Monthly precipitation samplesand meteorological data have been collected by the meteorologicalservices of more than eighty countries. For each of the 180 stationsselected for statistical treatment, numerical data and graphs arepresented, illustrating the most characteristic features of the accu-mulated isotope database.

Contents: Introduction; Statistical data; Data summary; Numericalstation index; Alphabetical station index; Laboratories which haveco-operated or are co-operating in the IAEA/WMO network.


THE APPLICATION OF THE PRINCIPLES FOR LIMITING RELEASES OF RADIOACTIVE EFFLUENTS IN THE CASE OF THE MINING AND MILLING OF RADIOACTIVE ORESSafety Series No. 90

This publication provides general guidance on the application ofSafety Series No. 77 (1986), Principles for Limiting Releases ofRadioactive Effluents into the Environment, to the setting of limitsfor the release of radioactive substances during the normal operationof the mining and milling of radioactive ores, as well as generalguidance on assessing the resulting individual and collective doses.

Contents: 1. Introduction; 2. Basic concepts; 3 Sources of radio-nuclide releases from uranium mining and milling facilities;4. Methodology for calculating doses to individuals resulting fromreleases; 5. Optimization of release control; 6. Guidance for appli-cation; Appendix.



PHYSICAL PROTECTION






Proceedings of an international conference jointly organized by theEC, IAEA, Interpol and WCO and held in Dijon, France, 14–18September 1998. The conference was the first of its kind devoted tothis subject and brought together radiation safety experts, regulators,and customs and police officers, in order to foster informationexchange through a review of the state of the art and open discus-sions. The need was expressed for the formulation of internationalrecommendations concerned with the effective operation of nationalsystems for ensuring the safety of radiation sources and the securityof radioactive materials. These proceedings contain the keynoteaddress, the invited papers, summaries of discussions and sessionsummaries. Together with IAEA-TECDOC-1045, published in 1998prior to the conference, they constitute the complete record of theconference.

Contents: Opening session; The problem; Response from interna-tional organizations; The regulatory control of radiation sources,including systems for notification, authorization (registration andlicensing) and inspection; Safety assessment techniques applied toradiation sources: Design and technological measures, includingdefence in depth and good engineering practice; Managerialmeasures, including safety culture, human factors, quality assur-ance, qualified experts, training and education; Learning from oper-ational experience; International co-operation, including reportingsystems and databases; Verification of compliance, monitoring ofcompliance: Assessment of the effectiveness of nationalprogrammes for the safety of sources, including development ofperformance indicators; Measures to prevent breaches in the secu-rity of radioactive materials (from production to disposal), experi-ence with criminal acts involving radioactive materials; Detectionand identification techniques for illicitly trafficked radioactive mate-rials (I and II); Response to detected cases and seized radioactivematerials, strengthening of the awareness, training, and exchange ofinformation; Summaries by chairpersons of the technical sessions.


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133

HISTORY OF THE INTERNATIONAL ATOMIC ENERGY AGENCY: The First Forty Years

This book, written by David Fischer and published by the IAEA inconjunction with the Monterey Institute of International Studies,California, covers the IAEA since its creation in 1957. The focus ofthe book is on the history of the IAEA as an organization inextrica-bly linked with the evolution of nuclear technology. Accordingly, thebook sketches the fortunes of nuclear power since 1957, the mainevents that have affected confidence in nuclear safety, and the evolu-tion of arms control, insofar as this has affected IAEA safeguards.Another major part of the IAEA’s work covered in the book is thetransfer of the practical applications of nuclear science to the devel-oping world. The IAEA’s main achievements and the setbacks it hasfaced are also described and assessed, as is the question of whetherthe organization has met its original aims.

Contents: Introduction; Part I — The creation of the IAEA: Eisen-hower proposes a new agency; 1939–1953: The dual challenge ofnuclear energy; 1954–1956: Negotiation of the IAEA’s statute; 1957— The Prepratory Commission and the first General Conference;Part II — 1957–1997: The IAEA in operation: A changing politicaland technical environment; The IAEA and nuclear power; Nuclearsafety and the management of nuclear waste; Nuclear safeguards;The transfer of nuclear technology to the developing world; TheIAEA and the applications of nuclear techniques (radioisotopes andradiation); The exchange of nuclear information; Part III — Issuesand conclusions: Issues; Conclusions; Annex 1: Statute of the Inter-national Atomic Energy Agency; Annex 2: “Atoms for Peace”;Annex 3: Selected statistical data; Glossary; Bibliography; Index.


INTERNATIONAL ATOMIC ENERGY AGENCY: Personal Reflections

This set of personal recollections reflect a variety of views fromtwenty-five distinguished scientists and diplomats who have playedmajor roles in shaping the policies of the IAEA or have madenotable contributions to its work at different periods of its history.The IAEA’s work is directly related to peace and security in theworld through the verification of commitments by States to usenuclear materials and installations exclusively for peacefulpurposes. This responsiblity is combined with a mandate to promotethe peaceful uses of nuclear energy — in such fields as nuclearpower, nuclear and radiation safety, and the applications of radiationand isotope techniques in agriculture, human health and hydrology.These ‘essays’ provide individual insights — often from a rarelyavailable insider’s perspective — into particular aspects of the devel-opment of an international organization and thus complement theHistory of the IAEA written by David Fischer.


HISTORY OF THE INTERNATIONAL ATOMIC ENERGY AGENCY: The First Forty Years

and

INTERNATIONAL ATOMIC ENERGY AGENCY: Personal Reflections

can be obtained at the special price for the set of both books for560 Austrian schillings (€40.70).

S P E C I A L P U B L I C A T I O N S

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135

NUCLEAR FUSION JOURNAL

A journal issued twelve times a year which includes original arti-cles, letters, review papers and comments in the field of controllednuclear fusion. Papers covering the following areas are published:plasma effects; processes and phenomena directly related to fusionresearch; production, heating and confinement of plasmas; applica-tion of experimental and diagnostic techniques to high temperatureplasmas; fusion reactor concepts and closely related technology.Special issues and supplements are published occasionally.

STI/PUB/23 (approx. 1800 pp./year, figures 21×30 cm)ISSN 0029–5515Price: Annual subscription (2000):

9900 Austrian schillings (€719.46)(surface mail and airmail delivery included)Special reduced price for individuals:1200 Austrian schillings (€87.21)(surface mail and airmal delivery included)Price per single issue: 940 Austrian schillings (€69.77)

P E R I O D I C A L S O F T H E I A E A

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TECHNICAL REPORT SERIES

188 STI/DOC/10/188 Radiological Safety Aspects of the Operationof Electron Linear Accelerators 15, 52, 64

240 STI/DOC/10/240 Guidebook on Spent Fuel Storage — 2nd Ed. 98

259 STI/DOC/10/259 Practical Borehole Logging Procedures forMineral Exploration with Emphasis on Uranium 20

262 STI/DOC/10/262 Manual on Training, Qualification andCertification of Quality Assurance Personnel 31, 90, 92

263 STI/DOC/10/263 An Oceanographic Model for the Dispersion ofWastes Disposed of in the Deep Sea 72, 77

264 STI/DOC/10/264 Environmental Isotope Data No. 8: World Surveyof Isotope Concentration in Precipitation (1980–1983) 22, 124

265 STI/DOC/10/265 Analysis of the Behaviour of Advanced ReactorPressure Vessel Steels under Neutron Irradiation 28, 86

266 STI/DOC/10/266 Engineering and Science Education for NuclearPower: A Guidebook 29, 91

267 STI/DOC/10/267 Methodology and Technology of DecommissioningNuclear Facilities 74, 104

268 STI/DOC/10/268 Manual on Maintenance of Systems andComponents Important to Safety 31, 86

269 STI/DOC/10/269 Economic Evaluation of Bids for Nuclear Power Plants,1986 Ed.: A Guidebook — superseded, see TRS No. 396

273 STI/DOC/10/273 Handbook on Nuclear Activation Data 17

274 STI/DOC/10/274 Design of Off Gas and Air Cleaning Systems at Nuclear Power Plants 29, 102

275 STI/DOC/10/275 Bid Invitation Specifications for NuclearPower Plants: A Guidebook 82

276 STI/DOC/10/276 Treatment, Conditioning and Disposal of Iodine-129 108

277 STI/DOC/10/277/2 Absorbed Dose Determination in Photon and Electron Beams: An International Code of Practice — 2nd Ed. (Also available in Spanish) 2, 13

278 STI/DOC/10/278 Methods for Reducing Occupational ExposuresDuring the Decommissioning of Nuclear Facilities 61, 74

279 STI/DOC/10/279 Nuclear Power Project Management: A Guidebook 84

280 STI/DOC/10/280 Training Courses on Radiation Protection out of print

281 STI/DOC/10/281 Developing Industrial Infrastructures to Supporta Programme of Nuclear Power: A Guidebook out of print

282 STI/DOC/10/282 Manual on Quality Assurance for ComputerSoftware Related to the Safety of Nuclear Power Plants out of print

137

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ES

SERIES INDEX

138

283 STI/DOC/10/283 Radiological Safety Aspects of the Operationof Proton Accelerators 15, 52, 65

284 STI/DOC/10/284 Geochemical Exploration for Uranium 19

285 STI/DOC/10/285 Guidelines on Calibration of Neutron Measuring Devices 13, 59

286 STI/DOC/10/286 Decontamination and Demolition of Concrete and Metal Structures During the Decommissioning of Nuclear Facilities out of print

287 STI/DOC/10/287 Treatment of Alpha Bearing Wastes 108

288 STI/DOC/10/288 Assessing the Impact of Deep Sea Disposal of Low Level Radioactive Waste on Living Marine Resources 72, 77, 122

289 STI/DOC/10/289 Immobilization of Low and Intermediate LevelRadioactive Wastes with Polymers 103

290 STI/DOC/10/290 Survey of Experience with Dry Storage of Spent Nuclear Fuel and Update of Wet Storage Experience 49, 99

291 STI/DOC/10/291 Design and Operation of Off-Gas Cleaning Systems at High Level Liquid Waste Conditioning Facilities 102

292 STI/DOC/10/292 Design and Operation of Off-Gas Cleaning andVentilation Systems in Facilities Handling Low and Intermediate Level Radioactive Material 102

293 STI/DOC/10/293 Factors Relevant to the Recycling or Reuse ofComponents Arising from the Decommissioning and Refurbishment of Nuclear Facilities 73, 102

294 STI/DOC/10/294 Options for the Treatment and Solidificationof Organic Radioactive Wastes 105

295 STI/DOC/10/295 Measurement of Radionuclides in Food and theEnvironment: A Guidebook 11, 60, 127

296 STI/DOC/10/296 Regulatory Inspection of the Implementation ofQuality Assurance Programmes: A Manual 47, 79, 91

297 STI/DOC/10/297 Flow Induced Vibrations in Liquid Metal FastBreeder Reactors 88

298 STI/DOC/10/298 Guidebook on Research and Development Support for Nuclear Power 83

299 STI/DOC/10/299 Review of Fuel Element Developments for WaterCooled Nuclear Power Reactors 96

300 STI/DOC/10/300 Cleanup of Large Areas Contaminated as aResult of a Nuclear Accident 68, 101

301 STI/DOC/10/301 Manual on Quality Assurance for Installationand Commissioning of Instrumentation,Control and Electrical Equipment in Nuclear Power Plants out of print

302 STI/DOC/10/302 Treatment of Off-Gas from Radioactive Waste Incinerators 109

303 STI/DOC/10/303 Radiation Preservation of Fish and Fishery Products 5

304 STI/DOC/10/304 Natural Analogues in Performance Assessmentsfor the Disposal of Long Lived Radioactive Wastes 56, 78

305 STI/DOC/10/305 Nuclear Fuel Cycle in the 1990s and Beyond theCentury: Some Trends and Foreseeable Problems 93

306 STI/DOC/10/306 Guidebook on the Education and Training ofTechnicians for Nuclear Power 30, 92

307 STI/DOC/10/307 Management of Abnormal Radioactive Wastes at Nuclear Power Plants 31, 74, 104

308 STI/DOC/10/308 Feasibility of Separation and Utilization of Ruthenium,Rhodium and Palladium from High Level Wastes 103

309 STI/DOC/10/309 Construction and Use of Calibration Facilitiesfor Radiometric Field Equipment 19

S E R I E S I N D E X

139

310 STI/DOC/10/310 The Environmental Behaviour of Radium out of print

311 STI/DOC/10/311 Environmental Isotope Data No. 9: World Surveyof Isotope Concentration in Precipitation (1984–1987) 22, 124

312 STI/DOC/10/312 Gas Cooled Reactor Design and Safety 30, 88

313 STI/DOC/10/313 Manual on Laboratory Testing for Uranium Ore Processing 95

314 STI/DOC/10/314 Guidebook on Design, Construction andOperation of Pilot Plants for Uranium Ore Processing 94

315 STI/DOC/10/315 Quality Management for Nuclear Power PlantOperation: A Manual 46, 79, 91

316 STI/DOC/10/316 Guidebook on Radioisotope Tracers in Industry 14, 24

317 STI/DOC/10/317 Implementation of Quality Assurance CorrectiveActions: A Manual 31, 79, 90

318 STI/DOC/10/318 Compendium of Neutron Spectra and DetectorResponses for Radiation Protection Purposes 17, 57

319 STI/DOC/10/319 Sealing of Underground Repositories for Radioactive Wastes 57, 107

320 STI/DOC/10/320 Evaluation of Spent Fuel as a Final Waste Form 97, 102

321 STI/DOC/10/321 Management of Severely Damaged Nuclear Fueland Related Waste 74, 98, 104

322 STI/DOC/10/322 Guidebook on Non-Destructive Examination ofWater Reactor Fuel 96

323 STI/DOC/10/323 Airborne Gamma Ray Spectrometer Surveying out of print

324 STI/DOC/10/324 Safe Handling of Tritium 65

325 STI/DOC/10/325 Particulate Filtration in Nuclear Facilities 105

326 STI/DOC/10/326 Conditioning of Alpha Bearing Wastes 101

327 STI/DOC/10/327 Planning for Cleanup of Large Areas Contaminated as a Result of a Nuclear Accident 70, 106

328 STI/DOC/10/328 Grading of Quality Assurance Requirements: A Manual out of print

329 STI/DOC/10/329 Laboratory Training Manual on the Use of Nuclear and Associated Techniques in Pesticide Residues 8, 127

330 STI/DOC/10/330 Disposal of Waste from the Cleanup of Large Areas Contaminated as a Result of a Nuclear Accident 68, 73, 102

331 STI/DOC/10/331 Statistical Treatment of Data on EnvironmentalIsotopes in Precipitation 22, 130

332 STI/DOC/10/332 Effects of Ionizing Radiation on Plants and Animals at Levels Implied by Current Radiation Protection Standards 58, 77, 123

333 STI/DOC/10/333 Measurement and Calculation of Radon Releasesfrom Uranium Mill Tailings 95

334 STI/DOC/10/334 Monitoring Programmes for Unrestricted ReleaseRelated to Decommissioning of Nuclear Facilities 105

335 STI/DOC/10/335 Current Practices for the Management andConfinement of Uranium Mill Tailings 94

336 STI/DOC/10/336 Laboratory Training Manual on the Use of Nuclear Techniques in Insect Research and Control — 3rd Ed. 5

337 STI/DOC/10/337 Chemical Precipitation Process for theTreatment of Aqueous Radioactive Waste 100

338 STI/DOC/10/338 Methodology for the Management of Ageing ofNuclear Power Plant Components Important to Safety 32

339 STI/DOC/10/339 Design and Operation of High Level WasteVitrification and Storage Facilities 73

340 STI/DOC/10/340 Quality Assurance Integrated Training Packages: A Manual 91, 92


140

341 STI/DOC/10/341 Analytical Techniques in Uranium Explorationand Ore Processing 19

342 STI/DOC/10/342 Performance of Engineered Barriers in DeepGeological Repositories 105

343 STI/DOC/10/343 Water Reactor Fuel Extended Burnup Study 96, 99

344 STI/DOC/10/344 Methods for the Estimation and EconomicEvaluation of Undiscovered Uranium Endowment and Resources: An Instruction Manual 20, 26

345 STI/DOC/10/345 Concepts for the Conditioning of Spent NuclearFuel for Final Waste Disposal 97

346 STI/DOC/10/346 Cleanup and Decommissioning of a NuclearReactor After a Severe Accident 100

347 STI/DOC/10/347 Coolant Technology of Water Cooled Reactors: An Overview 87

348 STI/DOC/10/348 Application of Remotely Operated Handling Equipment in the Decommissioning of Nuclear Facilities 99

349 STI/DOC/10/349 Report on Radioactive Waste Disposal 107

350 STI/DOC/10/350 Improved Cement Solidification of Low andIntermediate Level Radioactive Wastes 103

351 STI/DOC/10/351 Planning and Management for the Decommissioning of Research Reactors and Other Small Nuclear Facilities 106

352 STI/DOC/10/352 Bituminization Processes to Conditioning Radioactive Wastes 100

353 STI/DOC/10/353 Financing Arrangements for Nuclear Power Projects in Developing Countries: A Reference Book 83

354 STI/DOC/10/354 Reactivity Accidents 47, 78

355 STI/DOC/10/355 Containers for Packaging of Solid and Intermediate Level Radioactive Wastes 56, 101

356 STI/DOC/10/356 Feasibility of Separation and Utilization ofCaesium and Strontium from High Level Liquid Waste 97, 103

357 STI/DOC/10/357 Handbook on Nuclear Data for Borehole Loggingand Mineral Analysis (diskette incl.) 17, 19

358 STI/DOC/10/358 Off-Gas and Air Cleaning Systems for AccidentConditions in Nuclear Power Plants 89, 105

359 STI/DOC/10/359 Uranium Extraction Technology 21, 95

360 STI/DOC/10/360 Status of Technology for Volume Reduction andTreatment of Low and Intermediate Level Solid Radioactive Waste 108

361 STI/DOC/010/361 Cost Analysis Methodology of Spent Fuel Storage 97

362 STI/DOC/010/362 Decommissioning of Facilities for Mining and Milling of Radioactive Ores and Closeout of Residues 94, 101

363 STI/DOC/010/363 Guidelines for Agricultural Countermeasures Following an Accidental Release of Radionuclides 8, 69, 125

364 STI/DOC/010/364 Handbook of Parameter Values for the Prediction of Radionuclide Transfer in Temperate Environments 77, 125

365 STI/DOC/010/365 Decontamination of Water Cooled Reactors 87

366 STI/DOC/010/366 Assessment and Comparison of Waste Management System Costs for Nuclear and Other Energy Sources 100

367 STI/DOC/010/367 Software Important to Safety in Nuclear Power Plants 48

368 STI/DOC/010/368 Accident Management Programmes in NuclearPower Plants: A Guidebook 67

369 STI/DOC/010/369 Management for Excellence in Nuclear Power Plant Performance: A Manual 90


141

370 STI/DOC/010/370 Advances in Technologies for the Treatment ofLow and Intermediate Level Radioactive Liquid Wastes 99

371 STI/DOC/010/371 Environmental Isotope Data No. 10: World Survey of Isotope Concentration in Precipitation (1988–1991) 22, 124

372 STI/DOC/010/372 Development and Implementation of ComputerizedOperator Support Systems in Nuclear Installations 85, 88

373 STI/DOC/010/373 Decommissioning Techniques for Research Reactors 101

374 STI/DOC/010/374 Calibration of Dosimeters Used in Radiotherapy: A Manual out of print

375 STI/DOC/010/375 Safe Enclosure of Shutdown Nuclear Installations 47, 107

376 STI/DOC/010/376 Quality Assurance for Radioactive Waste Packages 106

377 STI/DOC/010/377 Minimization of Radioactive Waste from Nuclear Power Plants and the Back End of the Nuclear Fuel Cycle 104

378 STI/DOC/010/378 Options, Experience and Trends in Spent Fuel Management 98

379 STI/DOC/010/379 Design and Performance of WWER Fuel 95

380 STI/DOC/010/380 Nuclear Power Plant Personnel Training and ItsEvaluation: A Guidebook 92

381 STI/DOC/010/381 The Use of Plane Parallel Ionization Chambers in High Energy Electron and Photon Beams — An International Code of Practice 2

382 STI/DOC/010/382 Design and Construction of Nuclear Power Plants toFacilitate Decommissioning 28

383 STI/DOC/010/383 Characterization of Radioactive Waste Forms and Packages 53, 100

384 STI/DOC/010/384 Verification and Validation of Software Related to Nuclear Power Plant Instrumentation and Control 89

385 STI/DOC/010/385 Guidebook on Destructive Examination of Water Reactor Fuel 95

386 STI/DOC/010/386 Decommissioning of Nuclear Facilities Other than Reactors 101

387 STI/DOC/010/387 Modern Instrumentation and Control for Nuclear Power Plants: A Guidebook 89

388 STI/DOC/010/388 Review of Fuel Failures in Water Cooled Reactors 96

389 STI/DOC/010/389 Radiological Characterization of Shut Down NuclearReactors for Decommissioning Purposes 106

390 STI/DOC/010/390 Interim Storage of Radioactive Waste Packages 103

391 STI/DOC/010/391 Hydrogeological Investigation of Sites forGeological Disposal of Radioactive Wastes 22, 56

392 STI/DOC/010/392 Design Measures to Facilitate Implementationof Safeguards at Future Water Cooled Nuclear Power Plants 88, 114

393 STI/DOC/010/393 Nuclear Geophysics and Its Applications 12, 20

394 STI/DOC/010/394 Health and Environmental Impacts of ElectricityGenerated Systems: Procedures for Comparative Assessment 83, 125

395 STI/DOC/010/395 State of the Art Technology for Decontaminationand Dismantling of Nuclear Facilities 108

396 STI/DOC/010/396 Economic Evaluation of Bids for Nuclear Power Plants — 1999 Ed. 82


142

SAFETY SERIES

Publications available in Arabic (A), Chinese (C), English (E), French (F), Russian (R) and Spanish (S) are markedaccordingly.

6 STI/PUB/866 Regulations for the Safe Transport of RadioactiveMaterials, 1985 edition (As Amended 1990) (C,E,S) 55

7 STI/PUB/867 Explanatory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (1985 Edition) — Second Edition (As Amended 1990) (C,E,F,S) 54

35-S1 STI/PUB/927 Code on the Safety of Nuclear Research Reactors: Design (E,F,R,S) 14, 51

35-S2 STI/PUB/928 Code on the Safety of Nuclear Research Reactors: Operation (E,F,R,S) 15, 51

35-G1 STI/PUB/960 Safety Assessment of Research of ResearchReactors and Preparation of the Safety Analysis Report 16, 51

35-G2 STI/PUB/961 Safety in the Utilization and Modification of Research Reactors 16, 51

37 STI/PUB/868 Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (1985 edition), Third edition (As Amended 1990): A Safety Guide (C,E,S) 53

50 See NUSS (Nuclear Safety Standards) Programme p. 144

50-P See SAFETY PRACTICE Series withinthe NUSS Programme, p. 146

75 See INSAG Series, p. 149

77 STI/PUB/728 Principles for Limiting Releases of Radioactive Effluents into the Environment: A Safety Guide (C,F,R,S) 61, 128

78 STI/PUB/733 Definition and Recommendations for theConvention on the Prevention of Marine Pollution by Dumping of Wastes and other Matter, 1972-1986 Edition: A Safety Guide (E,F,R,S) 73, 118, 123

80 STI/PUB/869 Schedules of Requirements for the Transportof Specified Types of Radioactive Material Consignments (As Amended 1990): Companion Document to SS No. 6: A Safety Guide (C,E,R,S) 55

81 STI/PUB/751 Derived Intervention Levels for Application in Controlling Radiation Doses to the Publicin the Event of a Nuclear Accident or RadiologicalEmergency — Principles, Procedures and Data (R,S) 58, 68

85 STI/PUB/772 Safe Management of Wastes from the Mining and Milling of Uranium and Thorium Ores: A Safety Practice (E,F,R,S) 26, 74, 107

87 STI/PUB/773 Emergency Response Planning and Preparedness for Transport Accidents Involving Radioactive Material (E, S) 54, 69

88 STI/PUB/771 Medical Handling of Accidentally Exposed Individuals 60, 69

89 STI/PUB/817 Principles for the Exemption of Radiation Sources and Practices from Regulatory Control: A Safety Guide (E,F,R,S) 61, 74

90 STI/PUB/779 The Application of the Principles for Limiting Releases of Radioactive Effluents in the Case of the Mining and Milling of Radioactive Ores: A Safety Standard 26, 66, 130

91 STI/PUB/804 Emergency Planning and Preparedness forAccidents Involving Radioactive Materials Used in Medicine, Industry, Research and Teaching 52, 68


143

93 STI/PUB/801 Systems for Reporting Unusual Events inNuclear Power Plants: A Safety Guide (F,S) 49

95 STI/PUB/776 Radiation Monitoring in the Mining and Millingof Radioactive Ores: A Safety Guide 26, 62

96 STI/PUB/774 Guidance for Regulation of Underground Repositories for Disposal of Radioactive Wastes: A Safety Guide 56, 79

98 STI/PUB/812 On-Site Habitability in the Event of anAccident at a Nuclear Facility: Guidance for Assessment and Improvement: A Safety Guide 45, 69

99 STI/PUB/854 Safety Principles and Technical Criteria for the Underground Disposal of High Level Radioactive Wastes: A Safety Standard (E,F,R,S) 57, 75

100 STI/PUB/835 Evaluating the Reliability of Predictions Made Using Environmental Transfer Models: A Safety Practice 77, 125

101 STI/PUB/806 Operational Radiation Protection: A Guide toOptimization: A Safety Guide 61

103 STI/PUB/808 Provision of Operational Radiation Protection Services at Nuclear Power Plants: A Safety Practice 46, 62

104 STI/PUB/834 Extension of the Principles of RadiationProtection to Sources of Potential Exposure: A Safety Report 59

106 STI/PUB/911 The Role of Probabilistic Safety Assessment and Probabilistic Safety Criteria in Nuclear Power Plant Safety: A Safety Report 50, 78

107 STI/PUB/896 Radiation Safety of Gamma and ElectronIrradiation Facilities: A Safety Guide 52

108 STI/PUB/921 Design and Operation of Radioactive Waste Incineration Facilities 73

109 STI/PUB/900 Intervention Criteria in a Nuclear orRadiation Emergency: A Safety Guide (E,F,R,S) 60, 69

110 STI/PUB/938 The Safety of Nuclear Installations: A Safety Fundamental (E,F,R,S) 50

111-F STI/PUB/989 The Principles of Radioactive Waste Management: A Safety Fundamental (C,E,F,R,S) 75

111-G-1.1 STI/PUB/950 Classification of Radioactive Waste 100

111-G-3.1 STI/PUB/965 Siting of Near Surface Disposal Facilities: A Safety Guide 108

111-G-4.1 STI/PUB/952 Siting of Geological Disposal Facilities 75, 108

111-P-1.1 STI/PUB/924 Application of Exemption Principles to the Recycle and Reuse of Materials from Nuclear Facilities: A Safety Practice 72, 99

111-S-1 STI/PUB/990 Establishing a National System for Radioactive Waste Management: A Safety Standard (C,E,F,R,S) 73

112 STI/PUB/953 Compliance Assurance for the Safe Transport ofRadioactive Material: A Safety Practice 54

113 STI/PUB/958 Quality Assurance for the Safe Transport ofRadioactive Material: A Safety Practice 54, 79

114 STI/PUB/993 Direct Methods for Measuring Radionuclides in the Human Body 58

115 STI/PUB/996 International Basic Safety Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources: A Safety Standard (A,C,E,F,R,S) 59

STI/DAT/2 The Basic Safety Standards on Diskette 60

116 STI/PUB/976 Design of Spent Fuel Storage Facilities: A Safety Standard 27, 97

117 STI/PUB/977 Operation of Spent Fuel Storage Facilities: A Safety Standard 27, 98

118 STI/PUB/981 Safety Assessment for Spent Fuel Storage Facilities: A Safety Practice 75

119 STI/PUB/1014 Emergency Planning and Preparedness forRe-entry of a Nuclear Powered Satellite: A Safety Practice 68


144

120 STI/PUB/1000 Radiation Protection and the Safety of RadiationSources: A Safety Fundamental 52, 62

NUSS (Nuclear Safety Standards) PROGRAMME

Publications available in Chinese (C), English (E), French (F), Russian (R) and Spanish (S) are marked accordingly.

1 . G O V E R N M E N T A L O R G A N I Z A T I O N

Safety Code

50-C-G (Rev.1) STI/PUB/796 Code on the Safety of Nuclear Power Plants: Governmental Organization (C,E,F,R,S) 32, 79

Safety Guides

50-SG-G1 STI/PUB/513 Qualifications and Training of Staff of the Regulatory Body for Nuclear Power Plants: A Safety Guide (C,F,S) 33, 80

50-SG-G2 STI/PUB/515 Information to be Submitted in Support of Licensing Applications for Nuclear Power Plants: A Safety Guide (F,S) 33, 80

50-SG-G3 STI/PUB/571 Conduct of Regulatory Review and Assessment During the Licensing Process for Nuclear Power Plants: A Safety Guide (C,E,F,S) 33, 80

50-SG-G4 STI/PUB/1011 Inspection and Enforcement by the Regulatory Body for (Rev.1) Nuclear Power Plants: A Safety Guide (E) 33, 80

50-SG-G6 STI/PUB/601 Preparedness of Public Authorities for Emergencies at Nuclear Power Plants: A Safety Guide (C,E,F,S) 33, 70, 80

50-SG-G8 STI/PUB/620 Licences for Nuclear Power Plants: Content, Format and Legal Considerations: A Safety Guide (E,F,S) 34, 80

50-SG-G9 STI/PUB/676 Regulations and Guides for Nuclear PowerPlants: A Safety Guide (E,F,S) 34, 80

2 . S I T I N G

Safety Code

50-C-S (Rev.1) STI/PUB/797 Code on the Safety of Nuclear Power Plants: Siting (C,E,F,R,S) 34

Safety Guides

50-SG-S1 (Rev.1) STI/PUB/871 Earthquakes and Associated Topics in Relation to Nuclear Power Plant Siting: A Safety Guide (E,F,R,S) 34

50-SG-S3 STI/PUB/549 Atmospheric Dispersion in Nuclear PowerPlant Siting: A Safety Guide (C,E,S) 35, 122

50-SG-S4 STI/PUB/569 Site Selection and Evaluation for NuclearPower Plants with Respect to Population Distribution: A Safety Guide (C,E,F,S) 35

50-SG-S5 STI/PUB/585 External Man-Induced Events in Relation to Nuclear Power Plant Siting: A Safety Guide (C,E,F,S) 35

50-SG-S6 STI/PUB/539 Hydrological Dispersion of Radioactive Material in Relation to Nuclear Power Plant Siting: A Safety Guide (E,F,R,S) 35, 126

50-SG-S7 STI/PUB/677 Nuclear Power Plant Siting: Hydrogeological Aspects: A Safety Guide (E,F,R,S) 35, 127


145

50-SG-S8 STI/PUB/727 Safety Aspects of Foundations of NuclearPower Plants: A Safety Guide (E,F,R,S) 36

50-SG-S9 STI/PUB/682 Site Survey for Nuclear Power Plants: A Safety Guide (E,F,R,S) 36

50-SG-S10A STI/PUB/602 Design Basis Flood for Nuclear Power Plants on River Sites: A Safety Guide (E,F,R,S) 36

50-SG-S10B STI/PUB/655 Design Basis Flood for Nuclear Power Plants on Coastal Sites: A Safety Guide (E,F,R,S) 36

50-SG-S11A STI/PUB/614 Extreme Meteorological Events in Nuclear Power Plant Siting, Excluding Tropical Cyclones: A Safety Guide (E,F,S) 37

50-SG-S11B STI/PUB/666 Design Basis Tropical Cyclone for Nuclear Power Plants: A Safety Guide (E,F,R,S) 37

3 . D E S I G N

Safety Code

50-C-D (Rev.1) STI/PUB/798 Code on the Safety of Nuclear Power Plants: Design (C,E,F,S) 37, 87

Safety Guides

50-SG-D1 STI/PUB/542 Safety Functions and Component Classification for BWR, PWR, and PTR: A Safety Guide (C,E,F,S) 37

50-SG-D2 (Rev.1) STI/PUB/897 Fire Protection in Nuclear Power Plants: A Safety Guide (E,F,R,S) 37

50-SG-D3 STI/PUB/551 Protection Systems and Related Features in Nuclear Power Plants: A Safety Guide (C,E,F,S) 38

50-SG-D4 STI/PUB/552 Protection Against Internally Generated Missiles and Their Secondary Effects In Nuclear Power Plants: A Safety Guide (C,E,F,S) 38

50-SG-D5 (Rev.1) STI/PUB/984 External Man-Induced Events in Relation to Nuclear Power Plant: A Safety Guide (E,F,R,S) 38

50-SG-D6 STI/PUB/581 Ultimate Heat Sink and Directly Associated Heat Transport Systems for Nuclear Power Plants: A Safety Guide (E,C,F,S) 38

50-SG-D7 (Rev.1) STI/PUB/870 Emergency Power Systems at Nuclear Power Plants: A Safety Guide (E,F,R,S) 38

50-SG-D8 STI/PUB/678 Safety Related Instrumentation and Control Systems for Nuclear Power Plants: A Safety Guide (E,F,R,S) 39, 89

50-SG-D9 STI/PUB/687 Design Aspects of Radiation Protection for Nuclear Power Plants: A Safety Guide (C,E,F,R,S) 39, 58

50-SG-D10 STI/PUB/662 Fuel Handling and Storage Systems in Nuclear Power Plants: A Safety Guide (E,F,R,S) 39

50-SG-D11 STI/PUB/730 General Design Safety Principles for Nuclear Power Plants: A Safety Guide (E,F,R,S) 39

50-SG-D12 STI/PUB/693 Design of the Reactor Containment Systems in Nuclear Power Plants: A Safety Guide (E,F,R,S) 39

50-SG-D13 STI/PUB/731 Reactor Coolant and Associated Systems in Nuclear Power Plants: A Safety Guide (E,F,R,S) 40, 89

50-SG-D14 STI/PUB/732 Design for Reactor Core Safety in Nuclear Power Plants: A Safety Guide (E,F,R,S) 40, 87

50-SG-D15 STI/PUB/917 Seismic Design and Qualification for Nuclear Power Plants: A Safety Guide (E,F,R) 40


146

4 . O P E R A T I O N

Safety Code

50-C-O (Rev.1) STI/PUB/799 Code on the Safety of Nuclear Power Plants: Operation (C,E,F,R,S) 40, 84

Safety Guides

50-SG-O1 (Rev.1) STI/PUB/874 Staffing of Nuclear Power Plants and the Recruitment, Training and Authorization of Operating Personnel: A Safety Guide (E,F,R,S) 40, 92

50-SG-O2 STI/PUB/554 In-Service Inspection for Nuclear PowerPlants: A Safety Guide (C,F,S) 41, 85

50-SG-O3 STI/PUB/531 Operational Limits and Conditions for Nuclear Power Plants: A Safety Guide (C,F, S) 41, 86

50-SG-O4 STI/PUB/574 Commissioning Procedures for NuclearPower Plants: A Safety Guide (C,F,R,S) 41, 84

50-SG-O5 STI/PUB/654 Radiation Protection During Operation of Nuclear Power Plants: A Safety Guide (C,E,F,R,S) 41, 62

50-SG-O6 STI/PUB/618 Preparedness of the Operating Organization (Licensee) for Emergencies at Nuclear Power Plants: A Safety Guide (C,F,S) 41, 70

50-SG-O7 (Rev.1) STI/PUB/848 Maintenance of Nuclear Power Plants: A Safety Guide (C,E,F,R,S) 42, 85

50-SG-O8 (Rev.1) STI/PUB/849 Surveillance of Items Important to Safety in Nuclear Power Plants: A Safety Guide (C,E,F,R,S) 42

50-SG-O9 STI/PUB/660 Management of Nuclear Power Plants forSafe Operation: A Safety Guide (C,E,F,R,S) 42, 86

50-SG-O10 STI/PUB/685 Safety Aspects of Core Management and Fuel Handling for Nuclear Power Plants: A Safety Guide (E,F,R,S) 42

50-SG-O11 STI/PUB/734 Operational Management for Radioactive Effluents and Wastes Arising in Nuclear Power Plants: A Safety Guide (C,E,F,R,S) 43, 74, 105

50-SG-O12 STI/PUB/963 Periodic Safety Review Of OperationalNuclear Power Plants (E,F,R,S) 43

5 . Q U A L I T Y A S S U R A N C E

Code and Safety Guides

50-C/SG-Q STI/PUB/1016 Quality Assurance for Safety in Nuclear Power Plants and Other Nuclear Installations: Code and Safety Guides Q1-Q14 (E,F,R) 43, 79, 90

SAFETY PRACTICE SERIES within the NUSS (Nuclear Safety Standards) PROGRAMME

50-P-1 STI/PUB/819 Application of the Single Failure Criterion: A Safety Practice 43

50-P-2 STI/PUB/856 In-Service Inspection of Nuclear PowerPlants: A Safety Practice out of print

50-P-3 STI/PUB/902 Data Collection and Record Keeping for the Management of Nuclear Power Plant Ageing: A Safety Practice 44, 84

50-P-4 STI/PUB/888 Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants (Level 1): A Safety Practice 44

50-P-5 STI/PUB/887 Safety Assessment of Emergency PowerSystems for Nuclear Power Plants: A Safety Practice 44


147

50-P-6 STI/PUB/967 Inspection of Fire Protection Measures and Fire Fighting Capability at Nuclear Power Plants: A Safety Practice 44

50-P-7 STI/PUB/968 Treatment of External Hazards in Probabilistic Safety Assessments for Nuclear Power Plants: A Safety Practice 44, 78

50-P-8 STI/PUB/969 Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants (Level 2): Accident Progression, Containment Analysis and Estimation of Accident Source Terms: A Safety Practice 44, 78

50-P-9 STI/PUB/985 Evaluation of Fire Hazard Analyses for Nuclear Power Plants: A Safety Practice 45

50-P-10 STI/PUB/994 Human Reliability Analysis in Probabilistic Safety Assessment for Nuclear Power Plants: A Safety Practice 45, 78

50-P-11 STI/PUB/1007 Assessment of the Overall Fire SafetyArrangements at Nuclear Power Plants: A Safety Practice 45

50-P-12 STI/PUB/1009 Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants (Level 3): Off-site Consequences and Estimation of Risks to the Public: A Safety Practice 45, 78

SAFETY STANDARDS SERIES

Publications available in Arabic (A), Chinese (C), English (E), French (F), Russian (R) and Spanish (S) are markedaccordingly.

T R A N S P O R T S A F E T Y

Safety Requirements

TS-R-1 STI/PUB/1098 Regulations for the Safe Transport of Radioactive(ST-1, Revised) Material – 1996 Edition (Revised): Safety Requirements

(E,F,R,S) (A, C in preparation) 55

W A S T E S A F E T Y

NN ee aa rr SS uu rr ff aa cc ee DD ii ss pp oo ss aa ll oo ff RR aa dd ii oo aa cc tt ii vv ee WW aa ss tt ee

Safety Requirements

WS-R-1 STI/PUB/1073 Near Surface Disposal of Radioactive Waste: Safety Requirements (E) (A,C,F,R,S in preparation) 76

Safety Guides

WS-G-1.1 STI/PUB/1075 Safety Assessment for Near Surface Disposal of Radioactive Waste: Safety Guide (A,C,F,R,S in preparation) 76

PP rr ee dd ii ss pp oo ss aa ll MM aa nn aa gg ee mm ee nn tt oo ff RR aa dd ii oo aa cc tt ii vv ee WW aa ss tt ee II nn cc ll uu dd ii nn gg DD ee cc oo mm mm ii ss ss ii oo nn ii nn gg

Safety Requirements

forthcoming


148

Safety Guides

WS-G-2.1 STI/PUB/1079 Decommissioning of Nuclear Power Plants and Research Reactors: Safety Guide (E) (A,C,F,R,S in preparation) 76

WS-G-2.2 STI/PUB/1078 Decommissioning of Medical Industrial and Research Facilities: Safety Guide (E) (A,C,F,R,S in preparation) 76

R A D I A T I O N S A F E T Y

Safety Requirements

See STI/PUB/996 Safety Series No. 115: International Basic Safety Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources (A,C,E,F,R,S) 59

Safety Guides

RS-G-1.1 STI/PUB/1081 Occupational Radiation Protection: SafetyGuide (E) (A,C,F,R,S in preparation) 65

RS-G-1.2 STI/PUB/1077 Assessment of Occupational Exposure due to Intake of Radionuclides: Safety Guide (E) (A,C,F,R,S in preparation) 65

RS-G-1.3 STI/PUB/1076 Assessment of Occupational Exposure Due to External Sources of Radiation: Safety Guide (E) (A,C,F,R,S in preparation) 66

SAFETY REPORTS SERIES

1 STI/PUB/1039 Examples of Safety Culture Practices 30

2 STI/PUB/1040 Diagnosis and Treatment of Radiation Injuries 58, 68

3 STI/PUB/1052 Equipment Qualification in Operational NuclearPower Plants: Upgrading, Preserving and Reviewing 29

4 STI/PUB/1055 Planning the Medical Response to Radiological Accidents 70

5 STI/PUB/1056 Health Surveillance of Persons Occupationally Exposed to Ionizing Radiation: Guidance for Occupational Physicians 59

6 STI/PUB/107 Safety Issues for Advanced Protection, Control and Human–Machine Interface Systems in Operating Nuclear Power Plants 48, 86

7 STI/PUB/1058 Lessons Learned from Accidents in Industrial Radiography 69

8 STI/PUB/1059 Preparation of Fire Hazard Analyses for Nuclear Power Plants 46

9 STI/PUB/1061 Safe Handling and Storage of Plutonium 93

10 STI/PUB/1062 Treatment of Internal Fires in Probabilistic Safety Assessment for Nuclear Power Plants 50

11 STI/PUB/1064 Developing Safety Culture in Nuclear Activities —Practical Suggestions to Assist Progress 29

12 STI/PUB/1065 Evaluation of the Safety of Operating Nuclear Power Plants Built to Earlier Standards — A Common Basis for Judgement 29

13 STI/PUB/1066 Radiation Protection and Safety in Industrial Radiography 52

14 STI/PUB/1067 Assessment of Doses to the Public from Ingested Radionuclides 57

15 STI/PUB/1072 Implementation and Review of a Nuclear Power Plant Ageing Management Programme 31, 89


149

INSAG SERIES

Publications available in English (E), Chinese (C), French (F), Russian (R) and Spanish (S) are marked accordingly.

75-INSAG-1 STI/PUB/740 Summary Report on the Post-Accident Review Meeting on the Chernobyl Accident (E,F,R,S) 49, 78

75-INSAG-2 STI/PUB/770 Radionuclide Source Terms from Severe Accidents to Nuclear Power Plants with Light Water Reactors(E,F,R,S) 46, 78

75-INSAG-3 STI/PUB/802 Basic Safety Principles for NuclearPower Plants, superseded, see INSAG-12

75-INSAG-4 STI/PUB/882 Safety Culture (E,F,R,S) 48

75-INSAG-5 STI/PUB/910 The Safety of Nuclear Power (E,F,R,S) 50

75-INSAG-6 STI/PUB/916 Probabilistic Safety Assessment (E,F,R,S) 46

75-INSAG-7 STI/PUB/913 The Chernobyl Accident: Updating of INSAG-1 (E,F,R,S) 49, 78

INSAG-8 STI/PUB/991 A Common Basis for Judging the Safetyof Reactors Built to Earlier Standards (E,F,R,S) 27

INSAG-9 STI/PUB/992 Potential Exposure in Nuclear Reactor Safety (E,F,R,S) 45

INSAG-10 STI/PUB/1013 Defence in Depth in Nuclear Safety (E,F,R,S) 28, 77

INSAG-11 STI/PUB/1080 The Safe Management of Sources of Radiation:Principles and Strategies (E) (C,F,R,S planned) 53

INSAG-12 STI/PUB/1082 Basic Safety Principles for Nuclear Power Plants —75-INSAG-3 Rev. 1 (E) (F,R,S planned) 28

INSAG-13 STI/PUB/1083 Management of Operational Safety in NuclearPower Plants (E) (C,F,R,S planned) 31

INSAG-14 STI/PUB/1085 Safe Management of the Operating Lifetimesof Nuclear Power Plants (E) (C,F,R,S planned) 47

RADIOLOGICAL ASSESSMENT REPORTS SERIES

STI/PUB/1054 Radiological Conditions at Bikini Atoll: Prospectsfor Resettlement 63, 128

STI/PUB/1068 Radiological Conditions of the Western Kara Sea 63, 129

STI/PUB/1063 Radiological Conditions at the SemipalatinskTest Site, Kazakhstan: Preliminary Assessment and Recommendations for Further Study 63, 128

R E P O R T S O N T H E R A D I O L O G I C A L S I T U A T I O N A T T H E A T O L L S O F M U R U R O A A N D F A N G A T A U F A

STI/PUB/1028 The Radiological Situation at the Atolls of Mururoa and Fangataufa: Main Report (Executive Summary included) (E,F) 63–64, 129

STI/PUB/1028/ES The Radiological Situation at the Atolls ofMururoa and Fangataufa: Executive Summary (bilingual, E/F) 63, 129

STI/PUB/1029 The Radiological Situation at the Atolls ofMururoa and Fangataufa: Summary Report (E,F) 63–64, 130

INIS (INTERNATIONAL NUCLEAR INFORMATION SYSTEM) REFERENCE SERIES

1 IAEA-INIS-1 (Rev. 8) INIS: Guide to Bibliographic Description 119

2 IAEA-INIS-2 (Rev. 7) INIS: Samples for Bibliographic Description 119

3 IAEA-INIS-3 (Rev. 8) INIS: Subject Categories and Scope Descriptions 119


150

4 IAEA-INIS-4 (Rev. 2) INIS: Instructions for Submitting Abstracts 119

7 IAEA-INIS-7 (Rev. 3) INIS: Specifications for Machine ReadableData Exchange 120

11 IAEA-INIS-11 (Rev. 26) INIS: Authority List for Journal Titles 120

12 IAEA-INIS-12 (Rev. 3) INIS: Manual for Subject Analysis 120

13 IAEA-INIS-13 (Rev. 38) INIS: Thesaurus 120

13-S IAEA-INIS-13-S (Rev. 32) INIS: Thesaurus del SistemaInternacional de Documentación Nuclear 120

20 IAEA-INIS-20 (Rev. 1) Multilingual Dictionary (English part out of print)(French, German, Russian and Spanish partavailable) 120

22 IAEA-INIS-22 (Rev. 1) INIS: Database Manual 121

23 IAEA-INIS-23 INIS: FIBRE User’s Manual 121

LEGAL SERIES

3 STI/PUB/954 Agreements Registered with the InternationalAtomic Energy Agency — 11th Ed. 116

6 STI/PUB/274 Insurance for Nuclear Installations 116

7 STI/PUB/250 The Law and Practices of the International Atomic Energy Agency 116

7-S1 STI/PUB/942 The Law and Practices of the International Atomic Energy Agency 1970–1980. Supplement 1 116to the 1970 Edition of Legal Series No. 7

8 STI/PUB/333 Experience and Trends in Nuclear Law 116

9 STI/PUB/387 International Treaties Relating to NuclearControl and Disarmament 117

10 STI/PUB/421 Licensing and Regulatory Control of Nuclear Installations 117

11 STI/PUB/530 International Acceptance of Irradiated Food: Legal Aspects 117

13 STI/PUB/703 Réglementation des Activités Nucléaires 117

14 STI/PUB/765 Convention on Early Notification of a Nuclear Accident and Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency 117, 122

15 STI/PUB/850 Bilateral, Regional and Multilateral Agreements Relating to Co-operation in the Field of Nuclear Safety 117

16 STI/PUB/962 Convention on Nuclear Safety 117

IAEA REFERENCE DATA SERIES

IAEA-RDS-1/19 Energy, Electricity and Nuclear Power Estimates for the Period up to 2010 — July 1999 Ed. 83

IAEA-RDS-2/19 Nuclear Power Reactors in the World – April 1999 Ed. 81

IAEA-RDS-3/12 Nuclear Research Reactors in the World — December 1998 Ed. 15

IAEA SAFEGUARDS INFORMATION SERIES

IAEA/SG/INF/1 (Rev.1) IAEA Safeguards Glossary — 1987 Ed. 114

IAEA-SG/INF/2 IAEA Safeguards: Guidelines for States’ Systems of Accounting for and Control of Nuclear Materials 114

IAEA/SG/INF/6 IAEA Safeguards: Implementation at Nuclear Fuel Cycle Facilities 115


151

ATOMIC AND PLASMA-MATERIAL INTERACTION DATA FOR FUSION SERIES

STI/PUB/23/APID/01 Atomic and Plasma Material Interaction Data for Fusion, Vol. 1 11, 110






STI/PUB/23/APID/07/A Atomic and Plasma Material Interaction Data for Fusion, Vol. 7, Part A 12, 111


PERIODICALS OF THE IAEA

STI/PUB/23 Nuclear Fusion Journal 112, 135


BLANK

153

IND

EX

PUBLICATIONS DE L’AIEA EN LANGUE FRANÇAISE

COLLECTION SECURITE

7 STI/PUB/867 Commentaire des dispositions du règlement de transport des matières radioactives de l’AIEA (Edition de 1985). Deuxième édition (Revue en 1990) 54

35-S1 STI/PUB/927 Code pour la sûreté des réacteurs nucléaires de recherche: Conception 14, 51

35-S2 STI/PUB/928 Code pour la sûreté des réacteurs nucléaires de recherche: Exploitation 15, 51

50 Voir Programme NUSS, ci-dessous

75 Voir Collection INSAG, p. 156

77 STI/PUB/728 Principes de limitation des rejets d’effluents radioactifs dans l’environnement 61, 128

78 STI/PUB/733 Définition et recommandations pour la Convention sur la prévention de la pollution des mers résultant de l’immersion de déchets et autres matières, 1972. Edition de 1986 73, 118, 123

85 STI/PUB/722 Gestion des déchets des mines et des usines de traitement des minerais d’uranium et de thorium 26, 74, 107

89 STI/PUB/817 Principes pour l’exemption de contrôle réglementaire de sources et pratiques pouvant entraîner une radioexposition 61, 74

93 STI/PUB/801 Les systèmes de notification d’événements inhabituels survenant dans les centrales nucléaires 49

99 STI/PUB/854 Principes de sûreté et critères techniques pour le stockage définitif souterrain des déchets de haute activité 57, 75

109 STI/PUB/900 Critères d’intervention en cas de situationd’urgence nucléaire ou radiologique 60, 69

110 STI/PUB/938 La sûreté des installations nucléaires 50

111-F STI/PUB/989 Principes de gestion des déchets radioactifs 75

111-S-1 STI/PUB/990 Mise en place d’un système national de gestion des déchets radioactifs 73

115 STI/PUB/996 Normes fondamentales internationales de protection contre les rayonnements ionisants et de sûreté des sources de rayonnements 59

PROGRAMME NUSS

1 . O R G A N I S A T I O N G O U V E R N E M E N T A L E

50-C-G (Rev.1) STI/PUB/796 Code sur la sûreté des centrales nucléaires: Organisation gouvernementale 32, 79

154

Guides de sûreté

50-SG-G1 STI/PUB/513 Qualifications et formation du personnel de l’organisme réglementaire 33, 80

50-SG-G2 STI/PUB/515 Renseignements à fournir à l’appui des demandes d’autorisation pour les centrales nucléaires 33, 80

50-SG-G3 STI/PUB/571 Conduite de l’examen-évaluation réglementaire pendant la procédure d’autorisation pour les centrales nucléaires 33, 80

50-SG-G6 STI/PUB/601 Etat de préparation des pouvoirs publics pour les cas d’urgence dans les centrales nucléaires 33, 70, 80

50-SG-G8 STI/PUB/620 Autorisations relatives aux centrales nucléaires: Teneur, présentation et aspects juridiques 34, 80

50-SG-G9 STI/PUB/676 Règlements et guides relatifs aux centrales nucléaires 34, 80

2 . C H O I X D E S S I T E S

50-C-S (Rev.1) STI/PUB/797 Code sur la sûreté des centrales nucléaires: Choix des sites 34

Guides de sûreté

50-SG-S1 (Rev. 1) STI/PUB/871 Séismes et autres phénomènes connexes à prendre en considération pour le choix des sites de centrales nucléaires 34

50-SG-S4 STI/PUB/569 Choix et évaluation des sites de centrales nucléaires du point de vue de la répartition de la population 35

50-SG-S5 STI/PUB/585 Agressions externes dues aux activités humaines et choix des sites des centrales nucléaires 35

50-SG-S6 STI/PUB/539 Dispersion hydrologique des matières radioactives et choix des sites de centrales nucléaires 35, 126

50-SG-S7 STI/PUB/677 Choix des sites de centrales nucléaires — aspects hydrogéologiques 35, 127

50-SG-S8 STI/PUB/727 Les fondations des centrales nucléaires sous l’aspect de la sûreté 36

50-SG-S9 STI/PUB/682 Recherche et classement de sites de centrales nucléaires 36

50-SG-S10A STI/PUB/602 Crue de référence pour les sites de centrales nucléaires voisins de cours d’eau 36

50-SG-S10B STI/PUB/655 Niveau d’inondation de référence pour les sites côtiers de centrales nucléaires 36

50-SG-S11A STI/PUB/614 Phénomènes météorologiques extrêmes (cyclones tropicaux exceptés) et choix des sites de centrales nucléaires 37

50-SG-S11B STI/PUB/666 Cyclone tropical de référence et choix des sites de centrales nucléaires 37

3 . C O N C E P T I O N

50-C-D (Rev.1) STI/PUB/798 Code sur la sûreté des centrales nucléaires: Conception 37, 87

Guides de sûreté

50-SG-D1 STI/PUB/542 Fonctions de sûreté et classification des composants pour les réacteurs à eau bouillante, à eau sous pression et à tubes de force 37

50-SG-D2 (Rev. 1) STI/PUB/897 Protection contre l’incendie dans les centrales nucléaires 37

50-SG-D3 STI/PUB/551 Système de protection et dispositifs associés dans les centrales nucléaires 1981 38


155

50-SG-D4 STI/PUB/552 Protection des centrales nucléaires contre les projectiles d’origine interne et leurs effets secondaires 38

50-SG-D5 (Rev. 1) STI/PUB/984 Agressions externes dues aux activités humaines et conception des centrales nucléaires 38

50-SG-D6 STI/PUB/581 Source froide ultime et systèmes de transport de la chaleur directement associés pour les centrales nucléaires 38

50-SG-D7 (Rev.1) STI/PUB/870 Systèmes d’énergie de secours dans les centrales nucléaires 38

50-SG-D8 STI/PUB/678 Instrumentation et commande des centrales nucléaires 39, 89

50-SG-D9 STI/PUB/687 Conception de la protection radiologique dans les centrales nucléaires 39, 58

50-SG-D10 STI/PUB/662 Systèmes de manutention et de stockage du combustible dans les centrales nucléaires 39

50-SG-D11 STI/PUB/730 Principes généraux de sûreté dans la conception des centrales nucléaires 39

50-SG-D12 STI/PUB/693 Conception des systèmes de confinement des réacteurs de centrales nucléaires 39

50-SG-D13 STI/PUB/731 Systèmes de refroidissement du réacteur et systèmes associés dans les centrales nucléaires 40, 89

50-SG-D14 STI/PUB/732 Conception pour la sûreté du cœur des réacteurs de centrales nucléaires 40, 87

50-SG-D15 STI/PUB/917 Conception et homologation des constituants des centrales nucléaires du point de vue sismique 40

4 . E X P L O I T A T I O N

50-C-O (Rev.1)STI/PUB/799 Code sur la sûreté des centrales nucléaires: Exploitation 40, 84

Guides de sûreté

50-SG-O1 (Rev.1) STI/PUB/874 Personnel des centrales nucléaires: Recrutement, formation et habilitation des agents d’exploitation 40, 92

50-SG-O2 STI/PUB/554 Inspection en service des centrales nucléaires 41, 85

50-SG-O3 STI/PUB/531 Limites et conditions d’exploitation pour les centrales nucléaires 41, 86

50-SG-O4 STI/PUB/574 Procédures des essais de mise en service des centrales nucléaires 41, 84

50-SG-O5 STI/PUB/654 La radioprotection pendant l’exploitation des centrales nucléaires 41, 62

50-SG-O6 STI/PUB/618 Etat de préparation de l’organisme exploitant (du titulaire) pour les cas d’urgence dans les centrales nucléaires 41, 70

50-SG-O7 (Rev.1) STI/PUB/848 La maintenance des centrales nucléaires 42, 85

50-SG-O8 (Rev.1) STI/PUB/849 Surveillance des constituants importants pour la sûreté dans les centrales nucléaires 42

50-SG-O9 STI/PUB/660 Gestion des centrales nucléaires et sûreté d’exploitation 42, 86

50-SG-O10 STI/PUB/685 Gestion du cœur et manutention du combustible dans les centrales nucléaires 42

50-SG-O11 STI/PUB/734 Gestion des effluents et déchets radioactifs pendant l’exploitation des centrales nucléaires 43, 74, 105

50-SG-O12 STI/PUB/963 Bilan périodique de la sûreté des centrales nucléaires en service 43


156

5 . A S S U R A N C E D E L A Q U A L I T É

50-C/SG-Q STI/PUB/1016 L’ assurance de la qualité pour la sûreté des centrales nucléaires et autres installations nucléaires: Code et Guides de sûreté Q1-Q14 43, 79, 90

COLLECTION NORMES DE SÛRETÉ

S Û R E T É D E T R A N S P O R T

Prescription

ST-1 STI/PUB/998 Règlement de transport des matières radioactives — Edition de 1996/Prescription 55

COLLECTION INSAG

75-INSAG-1 STI/PUB/740 Rapport récapitulatif sur la réunion d’analyse de l’accident de Tchernobyl 49, 78

75-INSAG-2 STI/PUB/770 Le terme-source radioactif résultant d’accidents graves dans les centrales nucléaires équipées de réacteurs à eau ordinaire 46, 78

75-INSAG-3 STI/PUB/802 Principes fondamentaux de sûreté pour les centrales nucléaires, périmé, voir INSAG-12, p. 28

75-INSAG-4 STI/PUB/882 Culture de sûreté 48

75-INSAG-5 STI/PUB/910 Sûreté de l’énergie d’origine nucléaire 50

75-INSAG-6 STI/PUB/916 Etudes probabilistes de sûreté 46

75-INSAG-7 STI/PUB/913 L’accident de Tchernobyl: Mise à jour de INSAG-1 49, 78

INSAG-8 STI/PUB/991 Base commune pour juger du niveau de sûreté des centrales nucléaires construites conformément à des normes anciennes 27

INSAG-9 STI/PUB/992 L’exposition potentielle en sûreté nucléaire 45

INSAG-10 STI/PUB/1013 La défense en profondeur en sûreté nucléaire 28, 77

COLLECTION RAPPORTS D’EVALUATION RADIOLOGIQUES

STI/PUB/1028 Situation radiologique sur les atolls de Mururoa et de Fangataufa: Rapport principal 63-64, 129

STI/PUB/1028/ES Situation radiologique sur les atolls de Mururoa et de Fangataufa: Synthèse 63-64, 129

STI/PUB/1029 Situation radiologique sur les atolls de Mururoa et de Fangataufa: Rapport succint 63-64, 130

DIVERS

Collection juridique n° 13 STI/PUB/703 Réglementation des activités nucléaires 117

Collection juridique n° 14 STI/PUB/765 Convention sur la notification rapide d’un accident nucléaire et Convention sur l’assistance en cas d’accident nucléaire ou de situation d’urgence radiologique 117, 122

STI/PUB/815 L’accident radiologique de Goiânia 67, 71

STI/PUB/847 L’accident radiologique de San Salvador 67, 71


157

IND

EX

ПП УУ ББ ЛЛ ИИ КК АА ЦЦ ИИ ИИ ММ АА ГГ АА ТТ ЭЭ НН АА РР УУ СС СС КК ОО ММ ЯЯ ЗЗ ЫЫ КК ЕЕ

РУКОВОДСТВА ПО БЕЗОПАСНОСТИ

35-S1 STI/PUB/927 Свод положений по безопасности ядерных издается исследовательских реакторов: проектирование 14, 51

35-S2 STI/PUB/928 Свод положений по безопасности ядерных исследовательских реактров: эксплуатация 15, 51

50 См. ПРОГРАММА ПРНБ, стр. 158

75 См. СЕРИИ ИНСАГ, стр. 159

77 STI/PUB/728 Принципы ограничения выбросов радиоактивных веществ в окружающую среду 61, 128

78 STI/PUB/733 Определение и рекомендации для конвенции по предотвращению загрязнения моря сбросами отходов и других материалов, 1972 год. Издание 1986 года 73, 118, 123

80 STI/PUB/869 Перечни требований по перевозке определенных типов грузов радиоактивных веществ (исправлено в 1990 году) 55

81 STI/PUB/751 Производные уровни вмешательства, используемые для снижения доз облучения населения в случае ядерной аварии или радиационной аварийной ситуации: принципы, процедуры и данные 58, 68��

85 STI/PUB/772 Обращение с отходами при добыче и обработке урановых и ториевых руд 26, 74, 107

89 STI/PUB/817 Принципы изъятия источников излучения и видов работ из-под регулирующего контроля 61, 74

93 STI/PUB/801 Системы информации о необычных событиях на атомных электростанциях 49

99 STI/PUB/854 Принципы безопасности и технические критерии для подземного захоронения радиоактивных отходов высокого уровня активности 57, 75

109 STI/PUB/900 Критерии вмешательства в случае аварии или радиационной аварийной ситуации 60, 69��

110 STI/PUB/938 Безопасность ядерных установок 50

111-F STI/PUB/989 Принципы обращения с радиоактивными отходами 75

111-S-1 STI/PUB/990 Создание национальной системы для целей обращения срадиоактивными отходами 73

115 STI/PUB/996 Международные основные нормы безопасности для защиты от ионизирующих излучений и безопасного обращения с источниками излучения 59

158

ПРОГРАММА ПРНБ

1. П р а в и т е л ь с т в е н н а я о р г а н и з а ц и я

50-C-G (Rev. 1) STI/PUB/796 Свод положений по безопасности атомных электростанций: правительственная организация регулирования вопросов безопасности АЭС 32, 79

2 . В ы б о р п л о щ а д о к

50-C-S (Rеv. 1) STI/PUB/797 Свод положений по безопасности атомных электростанций: выбор площадок 34

Руководства по безопасности

50-SG-S1(Rev. 1) STI/PUB/871 Учет землетрясений и связанных с ними явлений при выборе площадок для атомных станций 34

50-SG-S6 STI/PUB/539 Учет параметров гидрологической дисперсии радиоактивных веществ при выборе площадок для атомных электростанций 35, 126

50-SG-S7 STI/PUB/677 Гидрогеологические аспекты выбора площадок для атомных электростанций 35, 127

50-SG-S8 STI/PUB/727 Аспекты безопасности оснований атомных электростанций 36

50-SG-S9 STI/PUB/682 Изыскание площадок для атомных электростанций 36

50-SG-S10A STI/PUB/602 Учет наводнений в основах проекта атомных электростанций, сооружаемых на берегах рек 36

50-SG-S10B STI/PUB/655 Учет наводнений в основах проекта атомных электростанций, сооружаемых на морском побережье 36

59-SG-S11B STI/PUB/666 Учет тропических циклонов в основах проекта атомных электростанций 37

3 . П р о е к т и р о в а н и е


50-SG-D2 (Rev. 1) STI/PUB/897 Противопожарная защита атомных станций 37

50-SG-D5 (Rev. 1) STI/PUB/984 Учет внешних событий, вызванных деятельностью человека, при проектировании атомных электростанций 38

50-SG-D7 (Rev. 1) STI/PUB/870 Системы аварийного энергоснабжения атомных электростанций 38

50-SG-D8 STI/PUB/678 Системы контрольно-измерительных приборов и управления, связанные с обеспечением безопасности атомных электростанций 39, 89

50-SG-D9 STI/PUB/687 Вопросы радиационной защиты в проектах атомных электростанций 39, 58

50-SG-D10 STI/PUB/662 Системы обращения с топливом и хранения его на атомных электростанциях 39

50-SG-D11 STI/PUB/730 Общие принципы безопасности, учитываемые при проектировании атомных электростанций 39

50-SG-D12 STI/PUB/693 Проектирование систем защитной оболочки реактора атомных электростанций 39

50-SG-D13 STI/PUB/731 Система теплоносителя реактора и связанные с ней системы атомных электростанций 40, 89


159

50-SG-D14 STI/PUB/732 Безопасность активной зоны реактора в проектах атомных электростанций 40, 87

50-SG-D15 STI/PUB/917 Проектирование и аттестация сейсмостойких конструкций для атомных станций 40

4 . Э к с п л у а т а ц и я

50-C-O (Rev. 1) STI/PUB/799 Свод положений по безопасности атомных электростанций: эксплуатация АЭС 40, 84


50-SG-O1 (Rev. 1) STI/PUB/874 Укомплектование кадрами атомных электростанций и подбор, профессиональная подготовка и допуск к работе 40, 92

50-SG-O4 STI/PUB/574 Порядок ввода атомных электростанций в эксплуатацию 41, 41, 84

50-SG-O5 STI/PUB/654 Радиационная защита при эксплуатации атомных электростанций 41, 62

50-SG-O7 (Rev. 1) STI/PUB/848 Техническое обслуживание атомных электростанций 42, 85

50-SG-O8 (Rev. 1) STI/PUB/849 Надзор за системами и узлами, важными для безопасности атомных электростанций 42

50-SG-O9 STI/PUB/660 Организация безопасной эксплуатации атомных электростанций 42, 86

50-SG-O10 STI/PUB/685 Вопросы безопасности при работе с активной зоной и обращении с топливом атомных электростанций 42

50-SG-O11 STI/PUB/734 Организация контроля радиоактивных выбросов и отходов в процессе эксплуатации атомных электростанций 43, 74, 105

50-SG-O12 STI/PUB/963 Периодическая оценка безопасности действующих АЭС 43

5 . О б е с п е ч е н и е к а ч е с т в а

50-C/SG-Q STI/PUB/1016 Обеспечение качества для безопасности атомных электростанций и других ядерных установок 43, 79, 90

СЕРИЯ НОРМ БЕЗОПАСНОСТИ

Б е з о п а с н о с т ь п е р е в о з к и

ST-1 STI/PUB/998 Правила безопасной перевозки радиоактивных материалов (издание 1996 г.) 55

СЕРИИ ИНСАГ

75-INSAG-1 STI/PUB/740 Итоговый доклад о совещании по рассмотрению причин и последствий аварии в Чернобыле 49, 78

75-INSAG-2 STI/PUB/770 Характеристики источника выброса радионуклидов при крупных авариях на атомных электростанциях с легководными реакторами 46, 78

75-INSAG-3 STI/PUB/802 Основные принципы безопасности атомных электростанций, замена, см. INSAG-12, стр. 28

75-INSAG-4 STI/PUB/882 Культура безопасности. Не переиздается 48

75-INSAG-5 STI/PUB/910 Безопасность ядерной энергетики 50

75-INSAG-6 STI/PUB/916 Вероятностный анализ безопасности 46

75-INSAG-7 STI/PUB/913 Чернобыльская авария: дополнение к INSAG-1 49, 78


160

INSAG-8 STI/PUB/991 Общая основа для оценки безопасности атомных электростанций, сооруженных в соответствии с ранее принятыми нормами 27

INSAG-9 STI/PUB/992 Потенциальное облучение и ядерная безопасность 45

INSAG-10 STI/PUB/1013 Глубокоэшелонированная защита в ядерной безопасности 28, 77

ДРУГИЕ ПУБЛИКАЦИИ

STI/PUB/885 Международный чернобыльский проект: Технический доклад 66-67, 78

STI/PUB/815 Радиационная авария в Гоянии 67, 71

STI/PUB/847 Радиационная авария в Сан-Сальвадоре 67, 71

STI/PUB/939 Укрепление инфраструктур в области радиационной и ядерной безопасности в странах бывшего СССР 80

STI/PUB/1015 Уроки аварий на промышленных облучательных установках 69

IAEA/SG/INF/1 (Rev. 1) Гарантии МАГАТЭ: Глоссарий. Издание 1987 года 114

IAEA/SG/INF/2 Гарантии МАГАТЭ: Руководящие принципы государственных систем учета и контроля ядерного материала 114

Серия изда STI/PUB/765 Конвенция об оперативном оповещении о ний по юри-ядерной аварии и Конвенция о помощи дическим в случае ядерной аварии или радиационной вопросам № 14 аварийной ситуации 117, 122


161

IND

EX

PUBLICACIONES DEL OIEA EN ESPAÑOL

COLECCION DE INFORMES TECNICOS

277/2 STI/DOC/010/277/2 Determinación de la dosis absorbida en haces de fotones y electrones – Código de Práctica Internacional – Segunda edición 2, 13

COLECCION SEGURIDAD

6 STI/PUB/866 Reglamento para el transporte seguro de materiales radiactivos. Edición de 1985 (enmendada en 1990) 55

7 STI/PUB/867 Manual explicativo para la aplicación del Reglamento del OIEA para el transporte seguro de materiales radiactivos (Edición de 1985). Segunda edición (enmendada en 1990) 54

35-S1 STI/PUB/927 Código sobre la seguridad de los reactores nucleares de investigación: Diseño 14, 51

35-S2 STI/PUB/928 Código sobre la seguridad de los reactores nucleares de investigación: Explotación 15, 51

37 STI/PUB/868 Manual de consulta para la aplicación del Reglamento del OIEA para el transporte seguro de materiales radiactivos (Edición de 1985) 53

50 Véase el programa NUSS, pág. 162

75 Véase la colección INSAG, pág. 164

77 STI/PUB/728 Principios para la limitación de las emisiones de efluentes radiactivos al medio ambiente 61, 128

78 STI/PUB/733 Definición y recomendaciones a los efectos del convenio sobre la prevención de la contaminación del mar por vertimiento de desechos y otras materias, 1972. Edición de 1986 73, 118, 123

80 STI/PUB/869 Esquemas sinópticos de los requisitos aplicables al transporte de tipos específicos de remesas de material radiactivo. (Edición enmendada en 1990) 55

81 STI/PUB/751 Niveles de intervención derivados para su aplicación al control de las dosis de radiación al público en caso de accidente nuclear o de emergencia radiológica. Principios, procedimientos y datos 58, 68

85 STI/PUB/772 Gestión segura de desechos en la minería y tratamiento de los minerales de uranio y de torio 26, 74, 107

87 STI/PUB/773 Planificación y preparación de la respuesta a emergencias debidas a accidentes de transporte en los que intervengan materiales radiactivos 54, 69

89 STI/PUB/817 Principios para la exención del control reglamentario de prácticas y fuentes de radiación 61, 74

162

93 STI/PUB/801 Sistemas para notificar sucesos no usuales ocurridos en centrales nucleares 49

99 STI/PUB/854 Principios y criterios técnicos de seguridad para la evacuación subterránea de desechos radiactivos de actividad alta 57, 75

109 STI/PUB/900 Criterios de intervención en caso de emergencia nuclear o radiológica 60, 69

110 STI/PUB/938 Seguridad de las instalaciones nucleares 50

111-F STI/PUB/989 Principios para la gestión de desechos radiactivos 75

111-S-1 STI/PUB/990 Establecimiento de un sistema nacional de gestión de desechos radiactivos 73

115 STI/PUB/996 Normas básicas internacionales de seguridad para la protección contra la radiación ionizante y para la seguridad de las fuentes de radiación 59

PROGRAMA NUSS

1 . O R G A N I Z A C I O N E S N A C I O N A L E S

50-C-G (Rev. 1) STI/PUB/796 Código sobre la seguridad de las centrales nucleares: Organizaciones nacionales 32, 79

Guías de seguridad

50-SG-G1 STI/PUB/513 Cualificaciones y capacitación del personal del órgano reglamentador de centrales nucleares 33, 80

50-SG-G2 STI/PUB/515 Información que ha de presentarse en apoyo de las solicitudes de licencia para centrales nucleares 33, 80

50-SG-G3 STI/PUB/571 Cumplimiento de los trámites reglamentarios de examen y evaluación durante el proceso de concesión de licencias para centrales nucleares 33, 80

50-SG-G6 STI/PUB/601 Medidas de las autoridades públicas en previsión de situaciones de emergencia en centrales nucleares 33, 70, 80

50-SG-G8 STI/PUB/620 Licencias para centrales nucleares: Contenido, forma y consideraciones jurídicas 34, 80

50-SG-G9 STI/PUB/676 Reglamentos y guías para centrales nucleares 34, 80

2 . E M P L A Z A M I E N T O

50-C-S (Rev. 1) STI/PUB/797 Código sobre la seguridad de las centrales nucleares: Emplazamiento 34

Guías de seguridad

50-SG-S1 (Rev. 1) STI/PUB/871 Terremotos y cuestiones conexas en relación con el emplazamiento de centrales nucleares 34

50-SG-S3 STI/PUB/549 Dispersión atmosférica en relación con el emplazamiento de centrales nucleares 35

50-SG-S4 STI/PUB/569 Selección y evaluación del emplazamiento de centrales nuclearesdesde el punto de vista de la distribución de la población 35

50-SG-S5 STI/PUB/585 Sucesos exteriores imputables al hombre en relación con el emplazamiento de centrales nucleares 35

50-SG-S6 STI/PUB/539 Dispersión hidrológica de sustancias radiactivas en relación con el emplazamiento de centrales nucleares 35


163

50-SG-S7 STI/PUB/677 Aspectos hidrogeológicos del emplazamiento de centrales nucleares 35, 127

50-SG-S8 STI/PUB/727 Aspectos de seguridad de la cimentación de centrales nucleares 36

50-SG-S9 STI/PUB/682 Estudio de emplazamientos para centrales nucleares 36

50-SG-S10A STI/PUB/602 Inundaciones tipo en el caso de centrales nucleares emplazadas junto a ríos 36

50-SG-S10B STI/PUB/655 Inundaciones tipo en el caso de centrales nucleares emplazadas en la costa 36

50-SG-S11A STI/PUB/614 Sucesos meteorológicos extremos en relación con el emplazamiento de centrales nucleares, excluidos los ciclones tropicales 37

50-SG-S11B STI/PUB/666 Ciclón tropical tipo para centrales nucleares 37

3 . D I S E Ñ O

50-C-D (Rev. 1) STI/PUB/798 Código sobre la seguridad de las centrales nucleares: Diseño 37, 87

Guías de seguridad

50-SG-D1 STI/PUB/542 Funciones de seguridad y clasificación de componentes de reactores de agua en ebullición, de agua a presión y de tubos de presión en centrales nucleares 37

50-SG-D2 (Rev. 1) STI/PUB/897 Protección contra incendios en centrales nucleares 37

50-SG-D3 STI/PUB/551 Sistema de protección y dispositivos conexos en centrales nucleares 38

50-SG-D4 STI/PUB/552 Protección contra proyectiles de procedencia interior y sus efectos secundarios en centrales nucleares 38

50-SG-D5 (Rev. 1) STI/PUB/984 Sucesos exteriores imputables al hombre en relación con el diseño de centrales nucleares 38

50-SG-D6 STI/PUB/581 Sumidero final de calor y sistemas directamente relacionados de transferencia de calor para centrales nucleares 38

50-SG-D7 (Rev.1) STI/PUB/870 Sistemas de emergencia de suministro de energía en centrales nucleares 38

50-SG-D8 STI/PUB/678 Sistemas de instrumentación y control de centrales nucleares relacionados con la seguridad 39, 89

50-SG-D9 STI/PUB/687 Cuestiones de diseño relacionadas con la protección radiológica en centrales nucleares 39, 58

50-SG-D10 STI/PUB/662 Sistemas de manipulación y almacenamiento del combustible en centrales nucleares 39

50-SG-D11 STI/PUB/730 Principios generales de diseño para la seguridad de centrales nucleares 39

50-SG-D12 STI/PUB/693 Diseño del sistema de contención de los reactores de centrales nucleares 39

50-SG-D13 STI/PUB/731 Sistemas de refrigeración de los reactores y sistemas asociados en las centrales nucleares 40, 89

50-SG-D14 STI/PUB/732 Diseño para la seguridad de los núcleos de reactores de centrales nucleares 40, 87

4 . E X P L O T A C I Ó N

50-C-O (Rev. 1) STI/PUB/799 Código sobre la seguridad de las centrales nucleares: Explotación 40, 84


164

Guías de seguridad

50-SG-O1 (Rev. 1) STI/PUB/874 Plantilla de personal para centrales nucleares y contratación, capacitación y autorización de su personal de explotación 40, 92

50-SG-O2 STI/PUB/554 Inspección durante el servicio en centrales nucleares 41, 85

50-SG-O3 STI/PUB/531 Límites y condiciones operacionales para centrales nucleares 41, 86

50-SG-O4 STI/PUB/574 Procedimientos de puesta en servicio para centrales nucleares 41, 41, 84

50-SG-O5 STI/PUB/654 Protección radiológica durante la explotación de centrales nucleares 41, 62

50-SG-O6 STI/PUB/618 Medidas de la entidad explotadora (concesionario de la licencia) para casos de emergencia en centrales nucleares 41, 70

50-SG-O7 (Rev. 1) STI/PUB/848 Mantenimiento de centrales nucleares 42, 85

50-SG-O8 (Rev. 1) STI/PUB/849 Vigilancia de elementos de importancia para la seguridad de centrales nucleares 42

50-SG-O9 STI/PUB/660 Gestión de centrales nucleares para su explotación en condiciones de seguridad 42, 86

50-SG-O10 STI/PUB/685 Aspectos de seguridad de la gestión del núcleo y de la manipulación del combustible en las centrales nucleares 42

50-SG-O11 STI/PUB/734 Gestión operacional de efluentes y desechos radiactivos procedentes de centrales nucleares 43, 74

50-SG-O12 STI/PUB/963 Examen periódico de seguridad de las centrales nucleares en explotación 43

COLECCION DE NORMAS DE SEGURIDAD

T R A N S P O R T E S E G U R O

Requisitos

ST-1 STI/PUB/998 Reglamento para el transporte seguro de materiales radiactivos — Edición de 1996/Requisitos 55

COLECCION INSAG

75-INSAG-1 STI/PUB/740 Informe resumido sobre la Reunión de examen a posteriori del accidente de Chernobil 49, 78

75-INSAG-2 STI/PUB/770 Términos fuente de radionucleidos provenientes de accidentes graves en centrales nucleares con reactores de agua ligera 46, 78

75-INSAG-3 STI/PUB/802 Principios básicos de seguridad para centrales nucleares; sustituido por INSAG-12 (pág. 28)

75-INSAG-4 STI/PUB/882 Cultura de la Seguridad 48

75-INSAG-5 STI/PUB/910 Seguridad de la energía nucleoeléctrica 50

75-INSAG-6 STI/PUB/916 Evaluación probabilista de la seguridad 46

75-INSAG-7 STI/PUB/913 El accidente de Chernobil: Actualización de INSAG-1 49, 78

INSAG-8 STI/PUB/991 Base común para juzgar la seguridad de las centrales nucleares construidas con arreglo a normas anteriores 27

INSAG-9 STI/PUB/992 La exposición potencial en seguridad nuclear 45

INSAG-10 STI/PUB/1013 La defensa en profundidad en seguridad nuclear 28, 77


165

DIVERSOS

Colección STI/PUB/765 Convención sobre la pronta notificación de accidentes jurídica N° 14 nucleares y Convención sobre asistencia en caso de

accidente nuclear o emergencia radiológica 117, 122

STI/PUB/815 El accidente radiológico de Goiânia 67, 71

STI/PUB/847 El accidente radiológico de San Salvador 67, 71

STI/PUB/1015 Enseñanzas deducidas de accidentes ocurridos en instalaciones de irradiación industrial 69

STI/PUB/1027 Sobreexposición accidental de pacientes de radioterapia en San José (Costa Rica)

Colección INIS IAEA-INIS-13/S Thesaurus del Sistema Internacional(Rev. 32) de Documentación Nuclear INIS 120


BLANK

Each title is listed under the first word. The numbers indicate the pages where the book is mentioned. Numbers in normal script meanthere is full entry on that page; numbers in italics mean that the book is mentioned by title only, although with a cross-reference tothe entry containing full detail. All titles published between 1 January 1996 and 1 January 2000 are printed in bold.

AA common basis for judging the safety of nuclear power plants built to earlier standards 27Absorbed dose determination in photon and electron beams: An international code of

practice — 2nd edition 2, 13Acceptance, control of and trade in irradiated food 4Accident management programmes in nuclear power plants: A guidebook 67Accidental overexposure of radiotherapy patients in San José, Costa Rica 57, 67Advanced nuclear power systems: Design, technology, safety and strategies for their deployment 82, 86Advances in technologies for the treatment of low and intermediate level radioactive liquid waste 99Advances in the operational safety of nuclear power plants 27Advisory material for the IAEA regulations for the safe transport of radioactive material

(1985 edition) — Third edition (as amended 1990) 53Agreements registered with the International Atomic Energy Agency 11th ed. 116An electron accelerator accident in Hanoi, Viet Nam 67An oceanographic model for the dispersion of wastes disposed of in the deep sea 72, 77Analysis of the behaviour of advanced reactor pressure vessel steels under neutron irradiation 28, 86Analytical techniques in uranium exploration and ore processing 19Application of exemption principles to the recycle and reuse of materials from nuclear facilities 72, 99Application of remotely operated handling equipment in the decommissioning of nuclear facilities 99Application of the single failure criterion: A safety practice 43Applications of isotopes and radiation in conservation of the environment 13, 14, 24, 122Asian regional co-operative project on food irradiation: Technology transfer 4Assessing the impact of deep sea disposal of low level radioactive waste on living marine resources 72, 77, 122Assessment and comparison of waste management system costs for nuclear and other energy sources 100Assessment of doses to the public from ingested radionuclides 57Assessment of occupational exposure due to external sources of radiation: Safety guide 66Assessment of occupational exposure due to intakes of radionuclides: Safety guide 65Assessment of the overall fire safety arrangements at nuclear power plants: A safety practice 45Atmospheric dispersion in nuclear power plant siting: A safety guide 35, 122Atomic and plasma–material interaction data for fusion (Supplement to the journal Nuclear Fusion) Volume 1 11, 110Atomic and plasma–material interaction data for fusion (Supplement to the journal Nuclear Fusion) Volume 2 11, 110Atomic and plasma–material interaction data for fusion (Supplement to the journal Nuclear Fusion) Volume 3 11, 110Atomic and plasma–material interaction data for fusion (Supplement to the journal Nuclear Fusion) Volume 4 12, 110

167

IND

EX

ALPHABETICAL INDEX 1986–1999

168

Atomic and plasma–material interaction data for fusion (Supplement to the journal Nuclear Fusion) Volume 5 12, 110Atomic and plasma–material interaction data for fusion (Supplement to the journal Nuclear Fusion) Volume 6 12, 111Atomic and plasma–material interaction data for fusion Volume 7, Part A 12, 111Atomic and plasma–material interaction data for fusion Volume 8 12, 111

BBack end of the nuclear fuel cycle: Strategies and options 96, 100Balancing automation and human action in nuclear power plants 28, 87Basic safety principles for nuclear power plants — 75-INSAG-3 Rev. 1 28Bilateral, regional and multilateral agreements relating to co-operation in the field of nuclear safety 117Bituminization processes to condition radioactive wastes 100

CCharacterization of radioactive waste forms and packages 53, 100Chemical precipitation processes for the treatment of aqueous radioactive waste 100Choosing the nuclear power option: Factors to be considered 82CIAMDA 87 16CIAMDA 98 16CINDA A (1935–1987) 16CINDA 97 17CINDA 99 17Classification of radioactive waste 100Cleanup and decommissioning of a nuclear reactor after a severe accident 100Cleanup of large areas contaminated as a result of a nuclear accident 68, 101Code on the safety of nuclear power plants: Design (Rev. 1) 37, 87Code on the safety of nuclear power plants: Governmental organization (Rev. 1) 32, 79Code on the safety of nuclear power plants: Operation (Rev. 1) 40, 84Code on the safety of nuclear power plants: Siting (Rev. 1) 34Code on the safety of nuclear research reactors: Design 14, 51Code on the safety of nuclear research reactors: Operation 15, 51Combination processes for food irradiation 4Commissioning procedures for nuclear power plants: A safety guide 41, 84Compendium of neutron spectra and detector responses for radiation protection purposes 17, 57Compliance assurance for the safe transport of radioactive material 54Concepts for the conditioning of spent nuclear fuel for final waste disposal 97Conditioning of alpha bearing wastes 101Conduct of regulatory review and assessment during the licensing process for nuclear power plants 33, 80Construction and use of calibration facilities for radiometric field equipment 19Containers for packaging of solid and intermediate level radioactive waste 56, 101Convention on early notification of a nuclear accident and convention on assistance in the case

of a nuclear accident or radiological emergency 117, 122Convention on nuclear safety 117Coolant technology of water cooled reactors: An overview 87Cost analysis methodology of spent fuel storage 97Cost-benefit aspects of food irradiation processing 4Current practices for the management and confinement of uranium mill tailings 94

K E Y W O R D I N D E X

169

DData collection and record keeping for the management of nuclear power plant ageing 44, 84Decommissioning of facilities for mining and milling of radioactive ores and closeout of residues 94, 101Decommissioning of medical, industrial and research facilities: Safety guide 76Decommissioning of nuclear facilities other than reactors 101Decommissioning of nuclear power plants and research reactors: Safety guide 76Decommissioning techniques for research reactors 101Design and construction of nuclear power plants to facilitate decommissioning 28Design and operation of high level waste vitrification and storage facilities 73Design and operation of off-gas cleaning and ventilation systems in facilities handling low

and intermediate level radioactive material 102Design and operation of off-gas cleaning systems at high level liquid waste conditioning facilities 102Design and operation of radioactive waste incineration facilities 73Design and performance of WWER fuel 95Design aspects of radiation protection for nuclear power plants: A safety guide 39, 58Design basis flood for nuclear power plants on coastal sites: A safety guide 36Design basis flood for nuclear power plants on river sites: A safety guide 36Design basis tropical cyclone for nuclear power plants: A safety guide 37Design for reactor core safety in nuclear power plants: A safety guide 40, 87Design measures to facilitate implementation of safeguards at future water cooled nuclear power plants 88, 114Design of off-gas and air cleaning systems at nuclear power plants 29, 102Design of spent fuel storage facilities 27, 97Design of the reactor containment systems in nuclear power plants: A safety guide 39Developing safety culture in nuclear activities — Practical suggestions to assist progress 29Development and implementation of computerized operator support systems in nuclear installations 85, 88Development of projects for the production of uranium concentrates 94Developments in radioimmunoassay and related procedures 1Diagnosis and treatment of radiation injuries 58, 68Direct methods for measuring radionuclides in the human body 58Directory of nuclear research reactors 1998 15Disposal of waste from the cleanup of large areas contaminated as a result of a nuclear accident 68, 73, 102Domestic buffalo production in Asia 9Dynamic functional studies in nuclear medicine in developing countries 1

EEarthquakes and associated topics in relation to nuclear power plant siting: A safety guide (Rev. 1) 34Economic evaluation of bids for nuclear power plants — 1999 edition 82Effects of ionizing radiation on plants and animals at levels implied by current radiation protection

standards 58, 77, 123Electricity and the environment 77, 81, 123Electricity, health and the environment: Comparative assessment in support of decision making 83Emergency planning and preparedness for accidents involving radioactive materials used in

medicine, industry, research and teaching 52, 68Emergency planning and preparedness for re-entry of a nuclear powered satellite 68Emergency power systems at nuclear power plants: A safety guide (Rev. 1) 38Emergency response planning and preparedness for transport accidents involving radioactive material 54, 69Energy, electricity and nuclear power estimates for the period up to 2020–July 1999 edition 83


170

Energy from inertial fusion 111Engineering and science education for nuclear power: A guidebook 29, 91Environmental behaviour of crop protection chemicals 8, 123Environmental contamination following a major nuclear accident 77, 124Environmental impact of radioactive releases 58, 124Environmental isotope data No. 8: World survey of isotope concentration in precipitation (1980-1983) 22, 124Environmental isotope data No. 9: World survey of isotope concentration in precipitation (1984-1987) 22, 124Environmental isotope data No. 10: World survey of isotope concentration in precipitation (1988-1991) 22, 124Equipment qualification in operational nuclear power plants: Upgrading, preserving and reviewing 29Establishing a national system for radioactive waste management 73Evaluating the reliability of predictions made using environmental transfer models 77, 125Evaluation of fire hazard analyses for nuclear power plants 45Evaluation of genetically altered medflies for use in sterile insect programmes 5Evaluation of spent fuel as a final waste form 97, 102Evaluation of the safety of operating nuclear power plants built to earlier standards —

A common basis for judgement 29Examples of safety culture practices 30Experience and trends in nuclear law 116Explanatory material for the IAEA regulations for the safe transport of radioactive material

(1985 edition) — Second edition (as amended 1990) 54Extension of the principles of radiation protection to sources of potential exposure 59External man-induced events in relation to nuclear power plants design: A safety guide 38External man-induced events in relation to nuclear power plant siting: A safety guide 35Extreme meteorological events in nuclear power plant siting, excluding tropical cyclones: A safety guide 37

FFactors relevant to the recycling or reuse of components arising from the decommissioning

and refurbishment of nuclear facilities 73, 102Fast breeder reactors: Experience and trends 88Feasibility of separation and utilization of caesium and strontium from high level liquid waste 97, 103Feasibility of separation and utilization of ruthenium, rhodium and palladium from high level wastes 103Feedback of operational safety experience from nuclear power plants 30, 85Feeding strategies for improving productivity of ruminant livestock in developing countries 9Financing arrangements for nuclear power projects in developing countries: A reference book 83Fire protection and fire fighting in nuclear installations 30Fire protection in nuclear power plants: A safety guide 37Flow induced vibrations in liquid metal fast breeder reactors 88Fuel handling and storage systems in nuclear power plants: A safety guide 27, 39Fusion energy 1996 111Fusion reactor design and rechnology 1986 112

GGamma, X-ray and neutron techniques for the coal industry 24Gas-cooled reactor design and safety 30, 88General design safety principles for nuclear power plants: A safety guide 39Genetic sexing of the Mediterranean fruit fly 5Geochemical exploration for uranium 19


171

Geological disposal of spent fuel and high level and alpha bearing wastes 56, 74, 97, 103Guidance for regulation of underground repositories for disposal of radioactive wastes 56, 79Guidebook on design, construction and operation of pilot plants for uranium ore processing 94Guidebook on destructive examination of water reactor fuel 95Guidebook on non-destructive examination of water reactor fuel 96Guidebook on radioisotope tracers in industry 14, 24Guidebook on research and development support for nuclear power 83Guidebook on spent fuel storage — Second edition 98Guidebook on the education and training of technicians for nuclear power 30, 92Guidelines for agricultural countermeasures following an accidental release of radionuclides 8, 69, 125Guidelines on calibration of neutron measuring devices 13, 59

HHandbook of parameter values for the prediction of radionuclide transfer in temperate environments 77, 125Handbook on nuclear activitation data 17Handbook on nuclear data for borehole logging and mineral analysis 17, 19Harmonization of health related environmental measurements using nuclear and isotopic techniques 14, 25, 125Health and environmental impacts of electricity generation systems: Procedures for

comparative assessment 83, 125Health surveillance of persons occupationally exposed to ionizing radiation: Guidance

for occupational physicians 59High dose dosimetry for radiation processing 13, 24History of the International Atomic Energy Agency: The first forty years 133Human reliability analysis in probabilistic safety assessment for nuclear power plants 45, 78Hydrogeological investigation of sites for the geological disposal of radioactive waste 22, 56Hydrological dispersion of radioactive material in relation to nuclear power plant siting: A safety guide 35, 126HyperTrans! 54

IIAEA safeguards glossary–1987 edition 114IAEA safeguards: Guidelines for states’ systems of accounting for and control of

nuclear materials facilities 114IAEA safeguards: Implementation at nuclear fuel cycle facilities 115Immobilization of low and intermediate level radioactive wastes with polymers 103Implementation and review of a nuclear power plant ageing management programme 31, 89Implementation of quality assurance corrective actions: A manual 31, 79, 90Improved cement solidification of low and intermediate level radioactive wastes 103Improvement of grain legume production using induced mutations 6Improvements in water reactor fuel technology and utilization 96In-service inspection for nuclear power plants: A safety guide 41, 85Information to be submitted in support of licensing applications for nuclear power plants 33, 80INIS: Authority list for journal titles 120INIS: Database manual 121INIS database on CD-ROM 119INIS: FIBRE user’s manual 121INIS: Guide to bibliographic description 119INIS: Instructions for submitting abstracts 119INIS: Manual for subject analysis 120


172

INIS: Multilingual dictionary 120INIS Non-conventional literature (NCL) on CD ROM 119INIS: Samples for bibliographic description 119INIS: Specifications for machine readable data exchange 120INIS: Subject categories and scope description 119INIS: Thesaurus 120Insect disinfestation of food and agricultural products by irradiation 4Inspection and enforcement by the regulatory body for nuclear power plants: A safety guide (Rev. 1) 33, 80Inspection of fire protection measures and fire fighting capability at nuclear power plants 44Insurance for nuclear installations 116Interim storage of radioactive waste packages 103International acceptance of irradiated food: Legal aspects 117International Atomic Energy Agency: Personal reflections 133International basic safety standards for protection against ionizing radiation and for the

safety of radiation sources 59International co-operation on nuclear waste management in the Russian Federation 103International nuclear safeguards 1994: Vision for the future 115International treaties relating to nuclear control and disarmament 117Intervention criteria in a nuclear or radiation emergency 60, 69Isotope aided studies on goat and sheep production in the tropics 9Isotope aided studies on livestock productivity in Mediterranean and North African countries 9Isotope aided studies on non-protein nitrogen and agro-industrial by-products utilisation by ruminants 9Isotope and related techniques in animal production and health 10Isotope techniques in the study of environmental change 22, 126Isotope techniques in the study of past and current environmental changes in the hydrosphere

and the atmosphere 22, 126Isotope techniques in water resources development 23, 126Isotope techniques in water resources development 1991 23, 126Isotopes in water resources management 23, 127

LLaboratory training manual on the use of nuclear and associated techniques in pesticide residues 8, 127Laboratory training manual on the use of nuclear techniques in insect research and control — 3rd edition 5Lessons learned from accidents in industrial irradiation facilities 69Lessons learned from accidents in industrial radiography 69Licences for nuclear power plants: Content, format and legal considerations: A safety guide 34, 80Licensing and regulatory control of nuclear installations 117Livestock reproduction in Latin America 10Low doses of ionizing radiation: Biological effects and regulatory control: Invited papers and discussions 60

MMaintenance of nuclear power plants: A safety guide (Rev. 1) 42, 85Man–machine interface in the nuclear industry 31, 85Management for excellence in nuclear power plant performance: A manual 90Management of abnormal radioactive wastes at nuclear power plants 31, 74, 104Management of insect pests: Nuclear and related molecular and genetic techniques 6Management of low and intermediate level radioactive wastes 74, 104


173

Management of nuclear power plants for safe operation: A safety guide 42, 86Management of operational safety in nuclear power plants 31Management of severely damaged nuclear fuel and related waste 74, 98, 104Manual on laboratory testing for uranium ore processing 95Manual on maintenance of systems and components important to safety 31, 86Manual on training, qualification and certification of quality assurance personnel 31, 90, 92Measurement and calculation of radon releases from uranium mill tailings 95Measurement assurance in dosimetry 2, 13Measurement of radionuclides in food and the environment: A guidebook 11, 60, 127Medical handling of accidentally exposed individuals 60, 69Metallogenesis of uranium deposits 20Methodology and technology of decommissioning nuclear facilities 74, 104Methodology for the management of ageing of nuclear power plants components important to safety 32Methods for reducing occupational exposures during the decommissioning of nuclear facilities 61, 74Methods for the estimation and economic evaluation of undiscovered uranium endowment and

resources: An instruction manual 20, 26Minimization of radioactive waste from nuclear power plants and the back end of the nuclear fuel cycle 104Modern instrumentation and control for nuclear power plants 89Monitoring programmes for unrestriced release related to decommissioning of nuclear facilities 105Multipurpose research reactors 15

NNatural analogues in performance assessments for the disposal of long lived radioactive wastes 56, 78Near surface disposal of radioactive waste: Safety requirements 76Nuclear and atomic data for radiotherapy and related radiobiology 2, 18Nuclear and related techniques for improving productivity of indigenous animals in harsh environments 10Nuclear communications: A handbook for guiding good communications practices at nuclear

fuel cycle facilities 93Nuclear desalination of sea water 84, 89Nuclear fuel cycle and reactor strategies: Adjusting to new realities 93Nuclear fuel cycle in the 1990s and beyond the century: Some trends and foreseeable problems 93Nuclear fusion journal 112, 135Nuclear fusion — Yokahama, special issue Nos. 1, 2, 3 112Nuclear geophysics and its applications 12, 20Nuclear medicine and related radionuclide applications in developing countries 1Nuclear power performance and safety 32, 81Nuclear power plant personnel training and its evaluation: A guidebook 92Nuclear power plant siting: Hydrogeological aspects: A safety guide 35, 127Nuclear power project management: A guidebook 84Nuclear power reactors in the world — April 1999 edition 81Nuclear research reactors in the world — December 1998 edition 15Nuclear safeguards technology 1986 115Nuclear techniques and in vitro culture for plant improvement 7Nuclear techniques in soil–plant studies for sustainable agriculture and environmental preservation 7, 127Nuclear techniques in the exploration and exploitation of energy and mineral resources 14, 20, 25Nuclear techniques in the study and control of parasitic diseases of livestock 10


174

OOccupational radiation protection: Safety guide 65Off-gas and air cleaning systems for accident conditions in nuclear power plants 89, 105On-site habitability in the event of an accident at a nuclear facility 45, 69One decade after Chernobyl: Summing up the consequences of the accident 61, 70Operating experience with nuclear power stations in Member States 1998 86Operation of spent fuel storage facilities 27, 98Operational limits and conditions for nuclear power plants: A safety guide 41, 86Operational management for radioactive effluents and wastes arising in nuclear power plants:

A safety guide 43, 74, 105Operational radiation protection: A guide to optimization 61Optimization of radiation protection 61Options, experience and trends in spent fuel management 98Options for the treatment and solidification of organic radioactive wastes 105

PParticulate filtration in nuclear facilities 105Performance of engineered barriers in deep geological repositories 105Periodic safety review of operational nuclear power plants: A safety guide 43Physical protection of nuclear materials: Experience in regulation,

implementation and operations 52, 115, 118, 131Planning and management for the decommissioning of research reactors and other small nuclear facilities 106Planning and operation of low level waste disposal facilities 106Planning for cleanup of large areas contaminated as a result of a nuclear accident 70, 106Planning the medical response to radiological accidents 70Plant domestication by induced mutation 7Plant mutation breeding for crop improvement 7Plasma physics and controlled nuclear fusion research 1988 112Plasma physics and controlled nuclear fusion research 1990 113Plasma physics and controlled nuclear fusion research 1992 113Plasma physics and controlled nuclear fusion research 1994 113Potential exposure in nuclear reactor safety 45Practical borehole logging procedures for mineral exploration with emphasis on uranium 20Preparation of fire hazard analyses for nuclear power plants 46Preparedness of public authorities for emergencies at nuclear power plants: A safety guide 33, 70, 80Preparedness of the operating organization (licensee) for emergencies at nuclear power plants:

A safety guide 41, 70Principles for limiting releases of radioactive effluents into the environment 61, 128Principles for the exemption of radiation sources and practices from regulatory control 61, 74Probabilistic safety assessment 46Procedures for conducting probabilistic safety assessments of nuclear power plants (Level 1) 44Procedures for conducting probabilistic safety assessments of nuclear power plants (Level 2):

Accident progression, containment analysis and estimation of accident source terms 44, 78Procedures for conducting probabilistic safety assessments of nuclear power plants (level 3):

Off-site consequences and estimation of risks to the public 45, 78Protection against internally generated missiles and their secondary effects in nuclear power plants:

A safety guide 38Protection systems and related features in nuclear power plants: A safety guide 38Provision of operational radiation protection services at nuclear power plants 46, 62


175

QQualifications and training of staff of the regulatory body for nuclear power plants: A safety guide 33, 80Quality assurance for radioactive waste packages 106Quality assurance for safety in nuclear power plants and other nuclear installations:

Code and safety guides Q1-Q14 43, 79, 90Quality assurance for the safe transport of radioactive material 54, 79Quality assurance integrated training packages: A manual 91, 92Quality management for nuclear power plant operation: A manual 46, 79, 91Quantification, nature and bioavailability of bound 14C pesticide residues in soil, plants and food 8, 128

RRadiation and society: Comprehending radiation risk 62Radiation induced F1 sterility in lepidoptera for area-wide control 6Radiation monitoring in the mining and milling of radioactive ores 26, 62Radiation preservation of fish and fishery products 5Radiation protection and safety in industrial radiography 52Radiation protection and the safety of radiation sources: A safety fundamental 52, 62Radiation protection during operation of nuclear power plants: A safety guide 41, 62Radiation protection in nuclear energy 62Radiation protection infrastructure 62, 80Radiation safety of gamma and electron irradiation facilities 52Radioactive waste management glossary 106Radiological characterization of shut down nuclear reactors for decommissioning purposes 106Radiological conditions at Bikini atoll: Prospects for resettlement 63, 128Radiological conditions at the Semipalatinsk test site, Kazakhstan: Preliminary assessment

and recommendations for further studies 63, 128Radiological conditions of the Western Kara Sea 63, 129Radiological safety aspects of the operation of electron linear accelerators 15, 52, 64Radiological safety aspects of the operation of proton accelerators 15, 52, 65Radionuclide source terms from severe accidents to nuclear power plants with light water reactors 46, 78Radiotherapy in developing countries 2Reactivity accidents 47, 78Reactor coolant and associated systems in nuclear power plants: A safety guide 40, 89Recognition of uranium provinces 21Recommended data on atomic collision processes involving iron and its ions 18, 112Recovery operations in the event of a nuclear accident or radiological emergency 47, 71Réglementations des activités nucléaires 117Regulations and guides for nuclear power plants: A safety guide 34, 80Regulations for the safe transport of radioactive material — 1985 edition (as amended 1990)Regulations for the safe transport of radioactive material — 1996 edition (revised):

Safety requirements 55Regulatory inspection of the implementation of quality assurance programmes: A manual 47, 79, 91Regulatory practices and safety standards for nuclear power plants 47, 80Report on radioactive waste disposal 107Review of fuel element developments for water cooled nuclear power reactors 96Review of fuel failures in water cooled reactors 96Reviewing the safety of existing nuclear power plants 47


176

SSafe enclosure of shut down nuclear installations 47, 107Safe handling and storage of plutonium 93Safe handling of tritium 65Safe management of wastes from the mining and milling of uranium and thorium ores 26, 74, 107Safety and engineering aspects of spent fuel storage 27, 98Safety aspects of core management and fuel handling for nuclear power plants: A safety guide 42Safety aspects of foundations of nuclear power plants: A safety guide 36Safety aspects of the ageing and maintenance of nuclear power plants 48Safety assessment for near surface disposal of radioactive waste: Safety guide 76Safety assessment for spent storage facilities 75Safety assessment of emergency power systems for nuclear plants 44Safety assessment of research reactors and preparation of the safety analysis report 16, 51Safety culture 48Safety functions and component classification for BWR, PWR and PTR: A safety guide 37Safety in the utilization and modification of research reactors 16, 51Safety issues for advanced protection, control and human-machine interface systems in

operating nuclear power plants 48, 86Safety of radiation sources and security of radioactive materials 52, 118, 131Safety principles and technical criteria for the underground disposal of high level radioactive wastes 57, 75Safety related instrumentation and control systems for nuclear power plants: A safety guide 39, 89Schedules of requirements for the transport of specified types of radioactive material

consignments (as amended 1990) 55Sealing of underground repositories for radioactive wastes 57, 107Seismic analysis and testing of nuclear power plants: A safety guide 34Seismic design and qualification for nuclear power plants: A safety guide 40Selected safety aspects of WWER-440 model 213 nuclear power plants 48Severe accidents in nuclear power plants 48, 78Site selection and evaluation for nuclear power plants with respect to population distribution:

A safety guide 35Site survey for nuclear power plants: A safety guide 36Siting of geological disposal facilities: A safety guide 75, 108Siting of near surface disposal facilities 108Software important to safety in nuclear power plants 48Source term evaluation for accident conditions 49, 78Stable isotopes in plant nutrition, soil fertility and environmental studies 7, 130Staffing of nuclear power plants and the recruitment, training and authorization of operating

personnel: A safety guide (Rev. 1) 40, 92State of the art technology for decontamination and dismantling of nuclear facilities 108Statistical treatment of data on environmental isotopes in precipitation 22, 130Status of technology for volume reduction and treatment of low and intermediate level

solid radioactive waste 108Sterile insect technique for tsetse control and eradication 6Strengthening radiation and nuclear safety infrastructures in countries of the former USSR 80Studies on sulphur isotope variations in nature 23Studies of the magnitude and nature of pesticide residues in stored products using radiotracer techniques 9Studies on the reproductive efficiency of cattle using radioimmunoassay techniques 10Summary report on the post-accident review meeting on the Chernobyl accident 49, 78Surveillance of items important to safety in nuclear power plants: A safety guide (Rev. 1) 42


177

Survey of experience with dry storage of spent nuclear fuel and update of wet storage experience 49, 99Systems for reporting unusual events in nuclear power plants 49

TThe application of the principles for limiting releases of radioactive effluents in the case of the

mining and milling of radioactive ores 26, 66, 130The basic safety standards on diskette 60The Chernobyl accident: Updating of INSAG-1 49, 78The international Chernobyl project: An overview 66, 78The international Chernobyl project: Proceedings 66, 78The international Chernobyl project: Technical report 67, 78The law and practices of the International Atomic Energy Agency 116The law and practices of the International Atomic Energy Agency, 1970-1980, Supplement 1 116The nuclear fuel cycle information system: A directory of nuclear fuel cycle facilities — 1996 edition 93The nuclear power option 82The principles of radioactive waste management: A safety fundamental 75The radiological accident at the irradiation facilty in Nesvizh 71The radiological accident in Goiânia 67, 71The radiological accident in San Salvador 67, 71The radiological accident in Soreq 53, 67, 71The radiological accident in Tammiku 67, 72The radiological accident in the reprocessing plant at Tomsk 67, 72The radiological situation at the atolls of Mururoa and Fangataufa: Executive summary 64, 129The radiological situation at the atolls of Mururoa and Fangataufa: Main report 64, 129The radiological situation at the atolls of Mururoa and Fangataufa: Summary report 64, 130The role of probabilistic safety assessment and probabilistic safety criteria in nuclear power plant safety 50, 78The safe management of sources of radiation: Principles and stragegies 53The safety of nuclear installations: A safety fundamental 50The safety of nuclear power 50The safety of nuclear power: Strategy for the future 50The use of plane parallel ionization chambers in high energy electron and photon beams —

An international code of practice for dosimetry 2Thesaurus del sistema internacional de documentación nuclear INIS 120Tomography in nuclear medicine 1Topical issues in nuclear radiation and radioactive waste safety 26Towards livestock disease diagnosis and control in the 21st century 10Treatment, conditioning and disposal of iodine-129 108Treatment of alpha bearing wastes 108Treatment of external hazards in probabilistic safety assessment for nuclear power plants 44, 78Treatment of internal fires in probabilistic safety assessment for nuclear power plants 50Treatment of off-gas from radioactive waste incinerators 109

UUltimate heat sink and directly associated heat transport systems for nuclear power plants: A safety guide 38Uranium deposits in Asia and the Pacific: Geology and exploration 21Uranium deposits in magmatic and metamorphic rocks 21Uranium extraction technology 21, 95


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Use of irradiation as a quarantine treatment of food and agricultural commodities 5Use of irradiation to control infectivity of food-borne parasites 5, 6Use of probabilistic safety assessment for operational safety PSA ‘91 51, 78

VVerification and validation of software related to nuclear power plant instrumentation and control 89

WWorld distribution of uranium deposits 21World survey of activities in controlled fusion research — 1997 edition 112

XX-ray and neutron techniques for the coal industry/Gamma, 24

YYokahama, special issue Nos. 1, 2, 3/Nuclear fusion — 112


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PUBLICATIONS BY SUBJECT - IAEA...computed tomography) and PET (positron emission tomography). SPECT is currently being used universally in clinical practice, while PET, orignally developed