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RADIATION SHIELDING INFORMATION CENTER
OAK RIDGE NATIONAL LAl3ORATORY DPERAIED BY UHlDf CARBIDE CORPDRLTIDN l FOR IME U.S. AlDllC EltERGY COYHISSIOH
POST OFFICE BOX X l
OAK RIDGE, TENNESSEE 37831
-
. f . SaM;tayana
EXECUTIVE COMMITTEE
The Shielding and Dosimetry Division of the American Nuclear Society will be led (1974-1975) by the following officers: David K. Trubey (ORNL-RSIC), Chairman; Edward A. Straker (SAL-Huntsville), Vice Chairman; Lawrence Harris (IRT-San Diego), Secretary; and Murray A. Schmoke (BRL), Treasurer. New members of the Executive Committee are: Gordon L. Brownell (MGH-Boston); Betty F. Maskewitz (ORNL-RSIC), and Arthur B. Chilton (U. Ill.). They join committee members: Anthony H. Foderaro (PSU); Siegfried A. W. Gerstl (ANL); Herbert Goldstein (Columbia U.); Charles M. Huddleston (NBS); Clyde P. Jupiter (EGEG); and Fred R. Mynatt (ORNL).
NAME CHANGE?
A study is presently being made to determine if a name change for the ANS Shielding and Dosimetry Division is in order. These efforts are being spurred by "shielders" in the power reactor design and operation business, They find themselves addressing radiation protection problems in plant design which require consideration of HVAC systems, piping systems, equipment layout, maintenance and decontamination, as well as calculating shield wall thicknesses.
The general field of radiation protection is already within the scope of the Shielding and Dosimetry Division activities. A proposed scope drafted by Eric Clarke and his group in 1968 included radiation protection as well as shielding and dosimetry as division responsibilities.
The Preamble reads as follows: "The Shielding and Dosimetry Division is con- cerned with promoting the free interchange of information and stimulating scien- tific research and engineering activities involving radiation shielding and dosimetry. The Shielding and Dosimetry Division provides a forum for persons en- gaged in research and engineering activities involving shielding and radiation."
The scope adopted by the division in November 1969 reads: "The Division shall devote itself specifically to the following aspects of nuclear science and technology: generation and transport of particulate and electromagnetic radiation; interaction of nuclear radiation with materials and biological systems, as it affects radiation transport and energy deposition; instruments and techniques for the measurement of nuclear radiation fields; radiation shield design and
IF YOU CHANGE YOUR ADDRESS, please notify us (including Building and Room No. where needed). ThirdClass Mail is returned to us at our expense if the addressee has moved. If your mail is returned, your name will be deleted from our distributions until we hear from you.
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evaluation; and radiation protection and
The present reemphasis of radiation
safety."
protection activities has sug- gested a name such as "Shielding and Radiation Protection Division." A straw vote will be taken via the Shielding and Dosimetry Division news- letter before a proposed name change will be placed on a final ballot,
Jerry Lahti, Sargent and Lundy, Chicago, is chairman of the ad hoc committee to look into a name change.
-- He will welcome your comments and
suggestions.
STUDENTS' SHIELDING DATA HANDBOOK
Jack Courtney is serving as the chairman of an ANS Shielding and Dosimetry Division ad hoc committee that has the objective of producing a students' handbook of shielding data. This document would present tables , graphs, and nomograms from a variety of sources in a low-cost format, Suggestions .from the shielding and radiation protection community on the content would be welcomed by Jack. He can be reached at: Nuclear Science Center, Louisiana State University, Baton Rouge, La. 70803.
WE NEED YOUR FEEDBACK
John M. Arras, Armed Forces Radiobiology Research Institute, writes the following: "I find the current format of the RSIC Newsletter quite satisfactory. The use of small block items is convenient, since the news- letters are bulky, and I rarely wish to order any item immediately, By cutting out individual items, I can add to my shielding (and related infor- mation) notebook, at the rate of several new items from each issue. This enables me to keep a current mini-bibliography, at least, more current than is possible with NSA. Also, I appreciate the inclusion of dosimetry, detector, and other information not directly related to shielding, since most of my problems are practical, rather than theoretical."
ENDF/B-TV DATA RELEASED
The fourth release of the Evaluated Nuclear Data File (ENDF/B-IV) is now in process. Five tapes have been released by the National Neutron Cross Section Center (NNCSC) at Brookhaven National Laboratory (BNL). The released data are ENDF/B tapes 401 (Rev. l), 402, 403, 404, and 405. The remaining tapes are expected to be released dver the next few months, Re- quests for this data should be made to BNL's NNCSC, not to RSIC.
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COMPUTER CODE COLLECTIOM (CCC) CtfANGES
Several changes were made to the code collection during the month.
CCC-SZD/ANISN-W The PERT-1D perturbation theory code employing linear first order techniques with multigroup angular de- pendent flux data from the ANISN-W discrete ordinates transport code has been contributed to RSIC by Westing- house Astronuclear Laboratory, It has been packaged as an auxiliary routine to CCC-82D/ANISN-W, operable on the CDC-6600. It may also be requested separately. A reel of magnetic tape is required for transmittal.
CCC-209/DOT III The Two-Dimensional Discrete Ordinates Radiation Trans- port Code package has been completely updated by ORNL to reflect development during the past year. GRTUNCL has been added as an auxiliary routine. A full reel of magnetic tape is required for transmittal.
CCC-222/TWOTRAN II The Two Dimensional Multigroup Discrete Ordinates Trans- port Code in (r,e) Geometry has been updated by LAS& to correct an error in the ordering cf the Sn constants. In all problems tested, the effect is small, but theoretic- ally the steeper the 6 flux gradient, the more pronounced the effect can be. However, in one problem with control rods, and consequently with very rapid 6 gradients, very little eigenvalue change was observed. In the TWOTRAN (r,0) geometry S4 test problems, the'eigenvalue change was less than 0.1%. Users should rerun typical problems of their own to assess the effect of the change. All versions of the code (IBM and CDC) have been corrected and are available from RSIC. A full reel of tape is required for transmittal.
CCC-232/CYGNUS-C Monte Carlo Neutron Transport Code in Spherical Geometry SPHERE has been contributed by Department of Nuclear Engineer-
ing, Kyoto University, Japan. FORTRAN IV.
CCC-161C/NMTC The CDC 6600/7600 versions of the Monte Carlo Nucleon- Meson Transport Code System has been updated by the Los Alamos Scientific Laboratory to correct errors and to reflect additional code development. A reel of magnetic tape must accompany a request for the new code package.
DO YOU WANT A COP!'
We have several copies of each of the following reports which we would like to put into circulation. Please let us know if you want a copy+
OPNL-TM-4464 (Feb. 1974) - "Gamma-Ray Production Due to Neutron Interactions with Zinc for Incident Neutron Energies Between 0.05 and 20 MeV: Tabulated Differential Cross Sections," J. K. Dickens, 'I. A. Love, G. L. Morgan, ORNL.
ORNL-4933 (January 1974) -, "Energy Deposition by 45-GeV Photons in H, 3e, Al, Cu, and Ta," R. G. Alsmiller, Jr., J. Barish, ORNL.
ORNL-TM-4538 (April 1974) - "Gamma Ray Production Due to Neutron Inter- actions With Fluorine and Lithium for Incident Neutron Energies Between 0.55 and 20 MeV: Tabulated Differential Cross Sections," J. K. Dickens, T. A. Love, G. L. Morgan, ORNL. '
ORAL-TM-4544 (May 1974) - "Gamma-Ray Production Due to Neutron Energies Between 0.8 and 20'MeV: Tabulated Differential Cross Sections," J. K. Dickens, T. A. Love, G. L. Morgan, ORNL.
ORNL-TM-3667 (January 1972) - "Monte Carlo Calculations of High-Energy Nucleon-Meson Cascades and Comparison With Experiment," T. W. Armstrong, R. G. Alsmiller, Jr., K. C. Chandler, and B. L. Bishop, ORNL.
ORNL-TM-4490 (March 1974) - "Calculated Physical and Biological Results When Negatively Charged Pions are Used to Irradiate a Small and a Large "Tumor" Volume in a Tissue Phantom," R. T. Santoro, R. G. Alsmiller, Jr., ORNL.
ORNL-TM-3659 (Rev.) (November 1972) -"Calculations of the Transport of Neutrons and Secondary Gamma Rays Through Concrete for Incident Neutrons in the Energy Range 15 to 75 MeV," R. W. Roussin, R. G. Alsmiller, Jr., J. Barish, ORNL.
ORNL-TM-4134 (January 1974)- "HIC-1: A First Approach to the Calculations of Heavy-Ion Reactions at Energies 2 50 MeV/Nucleon," H. W. Bertini, T. A. Gabriel, R. T. Santoro, 0. W. Hermann, N. M. Larson, J. M. Hunt, ORNL.
PRUCEEDTNGS OF THE THIRD TN'JERNATTONAL CODATA CONFERENCE
CODATA is the acronym of the Committee on Data for Science and Tech- nology of the International Council of Scientific Unions (ICSU). Pro- ceedings of the Third International CODATA Conference on Generation, Compilation, Evaluation and Dissemination of Data for Science and Tech- nology contain thirty-three of the contributions presented at the Confer- ence in Le Creusot, France, June 26-29, 1972. The topics covered in the Conference include: International Framework of CODATA; Progress of CODATA; Earth and Atmospheric Sciences; Biological Sciences; Astronomy and Astrophysics; Engineering Sciences; Computer Topics of Special Interest to Data Analysis Centers; Special Topics Important to Data Analysis Center Operations; and Accessibility and Dissemination of Critical Reviews and Dkta Compilations. The Proceedings are available for the price of $12.00 from CODATA Secretariat, 51 Boulevard de Montmorency, 75016 Paris, France.
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A new compilation In the area of high-energy physics from CERN, the European Organization for Nuclear Research, Geneva, Switzerland, is available to interested users in the Western Hemisphere and the Far East by writing to the Lawrence Radiation Laboratory, Berkeley, California 94720. CERN/HERA 73-1, 1.6. 1973, Compilation of Cross Sections III -p and p Induced Reactions, by E. Bracci, J. P. Drouley, E. Flaminio, J. D. Hansen and D. R. 0. Morrison is a compilation of cross sections of reactions produced by protons and antiprotons on targets of protons, neutrons and deuterons. This is an updated version of CERN/HERA 70-2 and 70-3 and contains forty percent more data values than the earlier publi- cations. Graphs of the variation of cross section with incident lab- oratory momentum are plotted. Values of the rate of decrease of cross section with incident momentum are provided.
We note the following changes in employment: Robert Burnside- from Westinghouse, Pittsburgh, to Florida Power and Light Company, Miami; Mike Nagel - from TRW to General Atomic, San Diego; William R. Yucker - from McDonnell Douglas Astronautics Corporation to Simulation Physics, Inc., Irvine, California; James (Jim) Stewart - from USAEC-DRRD to Los Alamos Scientific Laboratory, New Mexico; John Hobart - from McDonnell Douglas Astronautics to TRW Systems, Redondo Beach, California; Teruo Nagai - from National Institute of Radiological Sciences, Chiba, to Professor, Department of Radiological Sciences, Faculty of Medicine, Gunma University, Showa-machi, Maebashi, Japan.
The following changes of address have been noted: Yoshiharu Higashihara - from Power Reactor and Nuclear Fuel Development ~orp. to Nuclear Power Research and Development Department, Kawasaki Heavy Industries, Ltd., Wamamatsu-cho, Minato-ku, Tokyo, Japan; J. A. LonerRan, Science Applications, Inc., La Jolla,to Rolling Meadows, Ill.; Mr. R. Djetrich - from Krupp Maschinenfabriken - Kerntechnik, Essen, to Ges. F. Kernenergieverwertung in Schiffbau und Schiff"ahrt MBH, Institut F. Anlagentechnik, Geesthacht-Tesperhude, W. Germany; Austin A. O'Dell - M&sion Research Corp., Santa Barbara, to Lawrence Livermore Laboratory, Livermore, California; Dr. R. Ziskind - TRW Systems Group, Redondo Beach, California, to Science Applications, Inc., 101 Continental Bldg., El Segundo, California; Paul S. Pickard - from Nuclear Engineering Pro-' gram, University of Illinois at Urbana, to Reactor Studies Division, Sandia Laboratories, Albuquerque, N. M.
Andre Jacob, INRS-Energie, Varennes, Quebec, Canada, writes that h&s group is currently engaged in research in radiation damage and shielding for fusion reactors. They have used the ANISN code (CCC-821 for fusion reactor blanket simulation, and will use it with DLC-27 library for con- crete shielding calculations. The blanket simulation is completed and a copy of the results (Guy Lavergne Thesis) will be sent to RSIC.
Visitors to RSIC during the month of June were: R. W. Birkhahn, Brown, Boveri & CIE, Mannheim, W. Germany; K. D. George, Union Carbide Corporation, Tuxedo, New York; J. D. Gordon and R. Karcher, TRW, Redondo Beach and San Bernardino, Calif.; A. Pressesky, USAEC, Washington, D.C.
VIA PROCESSEV LI&RARY POCUMENTATIfXl
The new class of processed data libraries, first announced in the June 1, 1974 RSIC Newsletter, will be documented in ORNL-RSIC-37, "The Defense Nuclear Agency Processed Cross Section Library." It is planned that the report be a 3-ring binder and that the contents will be loose- leaf form to which additions can be made as new libraries are added to the DLC-31/DPL collection.
In order to help us estimate the number of binders to order, we will appreciate your completing the form below and returning it as soon as possible.
ORNL-RSIC-37
THE DEFENSE NUCLEAR AGENCY PROCESSED CROSS SECTION LIBRARY will be avail- able in a couple of months. Please return this coupon if you would like to receive a copy. Please reserve a copy of ORNL-RSIC-37 for:
(Name)
(Name of Installation)
(Address)
-I-
NNE ACCESSSON OF LITERATURE
THIS LITERATURE IS ON ORDEN. IT IS NOT IN OUR SYSTEM. PLEASE ORDER FROM NTIS OR OTHER AVAILABLE SOURCE AS IN=ATED.
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AEC-TR-74 32 Short Coursf? on Thermoelectric Devices and Their
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AECL-4591 Introduction to Radiation Protection Principles,
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ANL-AP/CTR/TM Fast Neutron Processes in Niobium - Measurements and
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!Jarch:It?!?* Argonne National Laboratory, Leaont, Ill,
ANL/RIY-72-1s 'Otal L'ne ShaKerative Non-Linear Least !&uares Spectra Uslag an
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* I isji Angermann, N. S. ; PebruaFi4fS
Danyluk, S.S. Dep.,
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AREAE -172 % .Study
51 g&ga= ,e Hussein
"%.m~~, I Atonic
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Dist Cadmium, Boron-Carbide and ower
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Noveaher*26:1973 NTIS
BURPNz;J;30 (Translation) : A Two-Dimensional SN Pro ram for Solving the
Ret angular f and
INDC(CCP)-33/L W;Ef-;na;i;n of Reqnir;: kccuracy of Nuclear Data.
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INDC(NDS)-55/L Cr ss Sections for P~SS~OU Neutron Spectrum 'Induced
React ohs. P Calauand, A. ;;
% genber, 1973
INDC(NDS)-56/B Proceedin s of a Consultants' Eeetin on Nuclear Data
&Reactor 1 eotron Dosimetry, Vienna, 3 O-12 September IiEA ;;;iuary,1974
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California 92138
iOUS of 6-Li and 10-B Between
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U!&EC'Technical Information Center, oak Ridge, Tenn.
and Code-Coordination Program. through December 3t,1973
Los Alamos Scientific Laboratory, Neu Hexico 87544
LA-U R-74-608 ; CONF-740402-15 Effect of BeJn,Zn) Multigroup Treatment on Theta-Pinch
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NASA-TH-X-71522; Thesis: N74-17424 Extension of CaseIs H&hod to the Tuo-Region Critical
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NASA-TR-R-472 Inalfsis of Laminated Co* osite
Shells with General Boanaary E Circular cylindrical
Srinivas S. ondittons,
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Publication 330, 7972 Ed, he InternatIonal System of Units (Sf).
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-lQ-
NOLTR-73-137 Computation of the f?e
forCt;qe;arp; Corps LVT Se tern&e '26 1973 Na t h al Or nan& Labora
flaryland 20910
al aad iat ion Traassission Factor
Dhit e Oak, Silver Spring,
NPL-NAC-99. 1970-15306 N aerlcal Quadrature. D&n, V.A.
A survey of Available Algorithms.
Jwd957 . a
ORWL-11909= ENDP-206 206-fib, 207-Pb and 208-Pb Neutron Blastic and Ine.lastic
&ctions from 5.50 to 8.50 HeV. .; Perey, P.G.
ORNL-T -Y474 P F uxes of Char ed and Neutral Particles fror Tokaaaks.
Hogan, J.T.; A ri1,1974
Clarke, J.P. N IS F
ORNL-TH-4544 Hagii~3~~"fX i
Prody tion t Incr ent
Due to NeutrQn Interaction Neutron Eoergles Betveen 0. 8 :fih
20 flev* Ddens
Tabglited DiffeFepial Cross Sectlons. 197t l
.; Luve, . .; Borgan, G.L. 335
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Annual Report, 7 wiments in the Geestbacht.Research Reactor.
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-11-
STI/DoC-~O-ffa2 Eva uat on of Radiation Emergencies and Accidents:
selected Criteria and Data.
STX/PUB-378 Beutron Monitoring for Radiation Protection Purposes,
vol. 1, (Proceedings of a Symposium, Vienna, It-15 DecF&r 1972).
1973 IAEA 616.00
Calculational nodels for LLL Pulsed S Shielding Benchmark Collection No, SDT 1
heres. Plechaty E.F.; Roverton, R.J. E.
CSEIG
W;ber,?973
DCRL-50400, Vol.7 Photonics A' "nteX?EPaE%E! Constants Graphical,
for Producti~~l~~~N~nt~~~~c~ and Rx eriaental Data for irajor
Int;;$~~~onD(R<!55 . L Rout&n-Tnduckd
Pertink .&.T;ight, R-C.; Roverton, R.J.; MacGregor, b n.Fl l
i'ril 1,1934 N IS 1
Acta Radio1 Ther Phys Biol 11 (6 Angula~'Distr~bution.~f Radigtion 5 593-602
Pha;k;;tzz os;dDt; Gattered froa a
R IO to 50 kvp Roentgen Rays.
Deceaber:19?2. .: Burlin, T.E.
htouic Data, 313 b
241-297 Survey of P &on-Attenuation-Coefficient Reasurenents
IO eV to 100 GeV. I:::f;b;,:sYi
Atomic Dpta aud Nncl. Data Tables, 13(2-3), 89-292 Radloactrve-Decay Gammas.
Nucl ide. Ordered by Energy aad
EE&~i%G l F!acF!urdo, R.1.
Atomic Data and Nucl. Data Tables, 1314) 293-337 Cow
P ilation
Par;E;eers. of Phenoaenological Opt&al-Bode1
1969-1972. .p:,~j~*: Percy, P.G.
hprl
Atomkernenergie Design of kn
22 21 h d
113-115 (In German) dlgional Shielding Layer for a Duct
in a.Concrete shieldgng Wall. op~%8;,%3
Yamajl, A.
-12-
Health Ph s., A no ;i et
26(4), 287-293 for Exposure to 8 Semi-Infinite cloud of a
'ho$~;t.~~lt;8;. l Snyder, U.S.
hprii, ‘1974 l l
Beta-Ray Dose. ; Lerc ., P.
Bealth Phys. 26(4), 313-338 ;;M&na~eSfor Radiation Protection.
l Garrett, U.R.; Payne, B.G, Apri1;19?4**
Int. J. Appl. Radiat. Isotop., 25(l), 25-29 neasareaent of Gamma-Ray Attenuation Coefficients. Christmas P. January,1474
Time-Dependent Spherical
J. nath. Aaal. Appl., 42(3), 578-593 Nonlinear Neutron-Transport Equations, Pa0 C.V. 1975
Kernenerge, 16(12) ra of KeuCt%%nsmitted Through Shields of
Difsf%ent ffa'e$i;tgs;ng Thicknesses. Ze”ZbeZ; i973 .
Kerntechnik, 15(10), $14-467 (In German) Build-up Factors for 14.1~UeV Neutrons in Different
Materials, oDE&l,$, hi3
Deieel, P,
Nucl. En *EN it a
Design, 25(3 t
325-333 - European iclear Documentation Service.
l(--L-~f;q g$jo l t Steven, G.
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Nucl. En Ava iabill J of 4
Des$ n, 25 3) 8 dncielZ'SZZ!dards Information.
cattrell W.B. August, 1474
Nucl. TEF%"f!k of if Finite
Methods 79 (2 5
224-220 ize Source on Angular
Distribution Attenoatian Coefficients. Elzlg;u; ,
5 B-A.; MacArthur, J.D.
,I970
Nucl. In&rum. wthods, tl7(1 93-99 Estimation of Gamma- I2
Fields b ay fposure in Nixed Gamma-Neutron
in Pair B 6-LiP and 7-L P Thermoluminescence Dosiaeters I
se. l Pumta, Y,
Nucl. Instrnm. Methods, 117(t), 99-107 Shaped Scintillataon Detector Systems for Measurements
of htZ;;iayJP:ux Rnlsotrop
uiiaes, it.+. l
.; vette, J.Z:: Stecker, P.w.; Eller, E.L,; Hay 1,1974
Nucl. nethods AI~%%%,rlo Hethod for talculation of the Distribution
117 (1) 125- 129
of Ionization Losses. Ispirian May l,f9$4
R.A.; Hatgarian, A.T.; Zverev, A,fl.
Nucl, Sci. Eng, ( 54 (2) 101-11s Relativistx Conpgon Scattering by the Discrete
Ordinates Ue;h;d. ;;;g;;ng’14 l l : Bridgman, C.J.
NUCl. sci. Eng., 54 (2 Single-Level Ana
116-126 sis
Section for Neutron of the Uranium-233 Fission Cross
nergies Between 6 and 124 eV. Nizaauddin, S.; Blbns, J. June,1974
Nucl. Sci. En Neutron 8-i
54 (2 u SW, s owing Down in Heavy Hedia Analysis iv 127-142
Pith Applicati;;Enof the Lead Spectrometer. r It.%.
ffeqts in Neutron e Time Spectra.
Nucl. PZtiEt s iL to Refir2&-1Z~&e Neutron Flux in Past 54 (2) -
l Daitch, P.R.
Nucl, Technology 22(2 Some Characterist i &
229-236 of Radioisotope Povet Sonrces
Nucl. Technolo y, 22(2 The ORNL B enchatar Lp f
275- 97 (ORNL-4880)
in Thic 1 Sodium. Exper aeut for Neutron Transport
~:ffr%t R.E.; Ruckenthaler, P.J.: Childs, R.L.
Phys. Rev. A, 8(6 Gamma-Ray it ikuation 1
2814-2838 Coefficient Heasoreaents.
Gopal Decea6ez;i973
San jeevaiah, B.
Phpi. fled. sio1., 19 2) !
171-l 85 ;k;giEifc$lREva uaCion of Plastic Dosimetry Phantoms. 1974 '
.; Schulz, R.3.
Report o N f lp
L Pro res 52-56 aad at on Sh P
1973 (Ott)
Satellites. eldfbg for
,yy,;g:;Q Qua&Z Crystal Oscillators in
;gjary, c l , R J
c -0
Rev.
BOOK
BOOK
Therm 7 85-96 EZnts ana'Coikretes !
In French) b3p;us;,3a.c.
or Nuclear Radiation Shielding.
AN INTRODUCTION TO RADIATIOH PROTECTION. Ha tin, A.; Harbison, S.A. 1952 fralsted Press 57.75 cloth: $4.75 paper
GLOSSARY OF TER!lS USED IN ""CL"~~nHtS",~"NC" AND TECHNOLOGY. ;;x&ish Standards Institution,
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COBPUTER CODES LITERATURE JAPPNR-97 n rch 1972 2D-GB?lFJA
ZD-GARBA: Two-Dinens f anal Gamma Heating code for Fast Reactors
Hltsubkshi Atomic Paver Industries, Inc., Omiya, Japan
IFA-NR41-1972 1972 23511 Multilevel Calculation of 23511 Neutron Fission Cross-
Section. llihallescu, I.R.; Petrascu, K. Institntul de Pizica Atomica, Bucharest, Romania FORTRAN IV
REDL-TBE-72-13U December 1972 3DP Bar&e 3DP A Thcee.D~~e;s~ou;lmPerturbation Theory code. Ranfora i Richland,
wag;&; ;;n !&:2beer ng bevGl;paent Laboratory,
3
ORNL-TH-4257 June 1973 ADLER-III ADLER-III: A Program to Calculate Cross Sections Prom
ADLEP-ADLER Resonance Parameters. P itional Laboratory, Oak Ridge, Tennessee
RT/FI-(73 39 h
October 1973 ANARA * A Code Using the La Grange's Hnltipliers nethod
fo:%ciear D?t;e;P Gan ini
e ?
Tztaent. Corn tat& iihionale p&rBivEnerqia Nucleare, Rome, Ttaly
""L-W;73 July 1973 APSAI : A Computer Code for Plotting Fluxes and Absorption
De;;;ikesSGenerated by the ANISN Code. ,_
oak Ridg;? National Laboratory, Oak Ridge, Tennessee
December 1972 ATTOY-B A New Version of Removal Diffusion Shielding
per I Energla kucleare, Rame, Italy L.i Toselli G.
AVAIL: NTIS (U.S. Sales Only)
KFK-1869 October 1973 ATTOW-K ATTOW-K: The Karls
Removal Diffusian Sh i uhe IB?l 360/65-Version of the 2D elding code ATTOU,
Boenisch, G.; Uiese, A.H. Kernforschnn szentrna Karlsruhe, Geraany ~;~,~f0~f~-,‘~~/;“’
. . Sales Only)
-J”s-
ORNL-4853 -'
NASA-TK-X-2836 !
OPEX-1D2C* A One-D i uly 1973 DOPEX- 1D2C
Sh ueusional, Tuo-Constraint Radiation
eld Optimization Code. k$%a~*!&ronautics and Space Administration, Lewis
Research Center, Cleveland, hi0 AVAIL: NTIS
u CRL-51493 No ember ETRANHS: A One-Dimens f
1973 ETRANH S onal Honte Carlo Electron/Photon
Transport Code for Multimaterial Targets. ~%%c~*~~vermore Laboratory, CDC 7600
Livermore, California AVAXL: NTIS
SLA-73-834 October 1973 EZTRANZ: A User&Orient d Version of the ETR~~T?!!2Zlectron-
Photon Monte Carlo Techn ",-I~
!a eib, J.A
f que. a Laborat&E&' Vandevender4 ~&~'Kexico
AVAIL: NTIS I Albuquerque,
JAERI-n-50 16 October 1972 FXT-I Computer Pro ram
Semiconductor % FIT-I for Pitting Gamma-Ray Spwtrua from
etectors.
3 Research Institute, Tokyo, Japan
ales Only)
RT/Pf-(73)16 ffay 1973 POUR ACES POUR ACES: A Prugraaae for Producin'g Groap Averaged Cross
Sections from Different Piles. Panjni CoiaitatoGbzGionale per 1fZnergia tiucleare, Bologna, Italy AVAIL: NTIS (U.S. Sales Only)
ORNL-TH-4296 ISODATA: A Computer
February 1974
contoars. Program for Calculati.nql%~~~!A
Anderson, V.E.: Ham Alsviller, R.G.f Jr.: &tNr&nq, T,Wf
- Turner J.E.; Wright, H.A.: g+kI;ld e National Laboratory, Oak Ridge, Tennessee
: ITIS
REAXE-tS8 197 -Legendre Hgments of Ne I kin’s Kernel for Wat%~!~!criptioa
..__. ----- - Abul-Ela
Atoa~~'E%~j Establishs%t, Cairo, Egypt FORTRAN AVAIL: NTIS (U.S. Sales Only)
--17-
ANU-P-584 December 1973 Programs for Ganaa-Ray Angular Distrihation~A~~~louing
toe 0nna Nuclear Reactions. TRorpsork, J.V.. AVATL: Austral;$fSNq$l$nal
. . Sa es P niversity, Canberra, Australia
Only)
ORNL-TR-4377 October 1973 mANYFILE CtANYF;ILE: A Computer Program for Use in the Manipulation
of Data Sets 3;t;een Various Input/Output Devices. Comolander t a.: Gryder, R.K. ;;: Ridge kational Laboratory, Oak Ridge, Tennessee AVAIL: NTIS
JAERI-FI-4721 march 1972 HICROSS -2 ACROSS-2: A Code fgr Calculation of nicroscopic and
Effgfo;;e gross Sections. Japan &toiic Energy Research Institute, Tokyo, Japan
ORNL-TPI-4429 JannaZ-t974
PI'XRDE Uedical X-Ray Dose Estiua Ion Program Progress Report
for Period Endin .Augnst 31, 1973.
Oak Ridge, Tennessee
IA- 1291 Novea ber 1973 NANTCS’ NAKED; NASIF s&f-;hielqed Gro;p Constants for Fast Reactor Caicnlations,
l Ylftah Tsr.&el*1toaic Eiier*~ %Z&n, AVAIL: NTIS (U.S. 3 ales Only)
Tel Aviv, Israel
IA- 1292 Novee ber 1973 Calcu!~%h of
Tel Aviv, Israel
RD/B/N-2572 February 1973 NSDA Unfolding Continuous Pulse
Johnson Board,*
* Poollaa P.3. BiknkGle*, Englind
““/“/W~;~ January 1973 ; A Honte Carlo Code for Est$.uating F!E%%light
Pt;~;;~~ltx;sCl~ ;a;;~sDl;e;sxonal Pin Cluster. Centra Iv El&Gicit AVAIL: NTIS (U.S. z
G&neia&ng Board, Berkeley, England ales Only)
LA-5433-HS December 1973 PIPL AN PIPLAH, A Treatment-Planning Code for Pions, Shlaer, U.J. M;I;ta;;mSScientific Laboratory, New Bexico
-18-
RT/FI- 72 48 d b
October'1972 PRAVDA P AV A Code for Ccc hini,
Gen E
G.P.; Cos r rating of Effective Cross Sections. l i, H.: Sa
Cm tato Nazionale pet l@Energ a Auclaare, Rome, Italy i vatores, Il.
AVAIL: NTIS (U.S. Sales Only]
Da-52
rZ January 1972
; ; E$eoofRaBCritical Assembly. PROTER; HUPT
Uinas Ge&& ;fniv., Be10 Aorizonte, Brazil
RCN-192 Se tember 1973 RCN-1 Error Anal
for Past Rea E sis of Neu ran Ca tar tors, Ap
Gruppe aar P P 1 ea to h3~fO~ PrOdUCtS.
Group Crass sections
%!%ri~'"ak&or Centr&a'~ederland, Petten, Netherlands AVAIL: N IS s (U.S. Sales Only)
KPKI-73-48 No Date Neutron Thggit?;zati;n Code RJT4-CiTHY.
RJT4-CATHY Gado Koz &nti'Pizikai
l El-Yak11 P AVA L:
i&a&& Intezet,'Buhapest, NTIS (U.S. Sales Only)
iungary
DNA-3197P RRF Ad
2 pint IYonte Carlo Gene
Pn;$o;tnsWf;c Czmplex of Radiation Response
Science ipblicaiions, Inc., La Jolla, Cadffj;iia * Lonergan, J.4.; Uoolson
KFR-1826 JUl 1973 SNOR SNOW: A Two-Dimensiona 3. SN-Program for Solvin
Transport-Equation in Recten nlar and Cylinder ii! the Neatron-
Guenther, C.; Kinnebrock, 5c eaaetrp.
;;;$g;;schungnentrum Karl&uhe, Germany AVAIL: NTIS (U.S. Sales Only)