Spent fuel characterization for geological repositories

Spent fuel characterization for geological repositories

Peter Jansson, Uppsala University

Presented at the 2015 symposium of theSwedish Centre for Nuclear Technology (SKC)

October 9With contributions from:

Alessandro Borella (SCK•CEN)Denis Janin (E.ON Kernkraft)Arjan Koning (NRG (IAEA))Malte Pettau (E.ON Technologies)

Marcus Seidl (E.ON Kernkraft)Henrik Sjöstrand (UU)Jean-Christophe Sublet (CCFE)

Outline

• Overview of geological disposal of high level waste.

• European council decision regarding Euratom research.⇒ IGD-TP

• Research prioritization by IGD-TP.

• About the SPIRE collaboration for spent fuel characterization.

• Some on-going and planned research projects.

● Launch into outer space

● Deposition below ice sheets

● Deep-sea sediment deposition

● Supervised storage● Geological disposal

Strategies

Geological disposal of high level waste.

Collect and keep separated from ecological systems.

Dilute to harmless concentrations and disperse.

● Ocean dumping

Principles

Used nuclear fuel

Resource

Waste

Reprocessing

● Long tunnels (VLH)

● WP-Cave● Deep Boreholes● KBS-3

Geological disposal systems

Adapted from SKB report P-14-20: http://www.skb.se/publication/2719413/P-14-20.pdf

http://www.skb.se/publication/2719413/P-14-20.pdf


URL 2015-10-06: https://en.wikipedia.org/wiki/Deep_geological_repository

Research facilities

https://en.wikipedia.org/wiki/Deep_geological_repository


URL 2015-10-06: https://en.wikipedia.org/wiki/Deep_geological_repository

Repositorysites

https://en.wikipedia.org/wiki/Deep_geological_repository

European council decision regarding Euratom research. ⇒ IGD-TP

European council decision 2006/976/EURATOM:

... the emphasis in Euratom research should be implementation-oriented R&D activities on all remaining key aspects of deep geological disposal of spent fuel and long-lived radioactive waste…

… demonstration of the technologies and safety…related to the management and disposal of waste are emphasised.


The instrument of European Technology Platforms (ETPs) have been introduced by EC to:

• Provide a framework for stakeholders, led by industry, to define research and development priorities.

• Play a key role in ensuring an adequate focus of research funding on areas with a high degree of industrial relevance.

• Address technological challenges that can potentially contribute to a number of key policy objectives which are essential for Europe's future competitiveness.


2006 → 2007Waste management organisations (WMO’s) in Europe performed a feasibility study:

“Co-ordination Action on Research, Development and Demonstration Priorities and Strategies for Geological Disposal (CARD)”

⇒ Technology platform for final disposal in deep geological formations launched in November 2009.

“Implementing Geological Disposal ofRadioactive Waste Technology Platform (IGD-TP)”

http://www.igdtp.eu

http://www.igdtp.eu


IGD-TP’s vision:

By 2025, the first geological disposal facilities for spent fuel, high-level waste, and other long-lived radioactive waste will be operating safely in Europe.

IGD-TP is committed to:

• build confidence in the safety of geological disposal solutions among European citizens and decision-makers;

• encourage the establishment of waste management programmes that integrate geological disposal as the accepted option for the safe long-term management of long-lived and/or high-level waste;

• facilitate access to expertise and technology and maintain competences in the field of geological disposal for the benefit of Member States.


IGD-TP’s Founding DocumentsVision

Strategic Research AgendaDeployment Plan

IGD-TP’s Exchange ForumExchange of information, advice,

discussions and proposals.

IGD-TP’s Executive GroupInitiates, decides, funds and directs IGD-TP,

establishes Working Groups.

IGD-TP’s SecretariatSupports IGD-TP’s activities, acts as communication and information centre. Follows up the deployment

of joint activities and updates the Master Deployment Plan. Reports to the EC.

Joint Activity Types for

Deploymentaccording to MDP

Terms of Reference of IGD-

TPWorking Groups

Coordination with EC

Euratom Framework Programme

Adapted from the IGD-TP flyer (2015-10-06): http://www.igdtp.eu/index.php/key-documents/doc_download/276-igd-tp-flyer-2014

http://www.igdtp.eu/index.php/key-documents/doc_download/276-igd-tp-flyer-2014


Countries participating in IGD-TP as of October 6AustraliaBelgium (BE)Canada (CA)Czech Republic (CZ)Finland (FI)France (FR)Germany (DE)Greece (GR)Hungary (HU)International OrganisationsItaly (IT)Japan (JP)

Lithuania (LT)Poland (PL)Portugal (PT)Romania (RO)Serbia (RS)Slovakia (SK)Slovenia (SI)Spain (ES)Sweden (SE)Switzerland (CH)The Netherlands (NL)Ukraine (UA)United Kingdom (GB)


Tellus Holdings Ltd

AREVA

EIG EURIDICE

ONDRAF/NIRAS

SCK · CEN

NWMO

Centrum výzkumu řež, s.r.o.

Czech Technical University in Prague

Nuclear Research Institute Rez (UJV)

SURAO

Technical University of Liberec

Aalto University Foundation

B+Tech Oy

Posiva Oy

Saanio & Riekkola Consulting Engineers

VTT Technical Research Centre of Finland

Bureau de Recherches Géologiques et Minières (BRGM)

CEA

Centre national de la recherche scientifique (CNRS)

GEM - Groupe des Ecoles des Mines

INERIS

INRIA

Institut National Polytechnique de Lorraine (INPL)

Laboratoire national de métrologie et d'essais (LNE)

Nidia srl

Université de Technologie de Troyes (UTT)

Université de Versailles St. Quentin-en-Yvelines

BMWi

Bundesanstalt für Geowissenschaften und Rohstoffe

Bundesanstalt für Materialforschung und -prüfung (BAM)

DBE TECHNOLOGY GmbH

Federal Office for Radiation Protection (BfS)

Forschungszentrum Jülich

Gesellschaft für Anlagen- und Reaktorsicherheit mbH (GRS)

Gesellschaft für Nuklear-Service mbH (GNS)

Helmholtz-Zentrum Dresden-Rossendorf, Institute of Resource Ecology

Hydroisotop GmbH

Institute of Disposal Research - Clausthal University of Technology

Karlsruhe Institute of Technology (KIT)

NUKEM Technologies GmbH

S & B Industrial Minerals GmbH

Steinbeis GmbH

Technische Universität Bergakademie Freiberg

Technische Universität Braunschweig

Universität des Saarlandes

VGB PowerTech e.V.

S&B Industrial Minerals S.A.

GEOCHEM Ltd.

KFKI Atomic Energy Research Institute

National Research Institute for Radiobiology and Radiohygiene (NRIRR)

PURAM

EuroGeoSurveys

European Commission,Joint Research Center (JRC), Institute for Transuranium Elements

European Nuclear Society (ENS)

European Repository Development Organization Working Group

FORATOM

ENEA

Inter-University Consortium for Nuclear Technological Research (CIRTEN)

Istituto Nazionale di Fisica Nucleare (INFN)

Istituto Nazionale di Oceanografia e di Geofisica Sperimentale (OGS)

University of Milan

RWMC

Lithuanian Energy Institute

Institute of Nuclear Chemistry and Technology

Mineral and Energy Economy Research Institute of the Polish Academy of Sciences

Radioactive waste management plant

IST/CTN, Technical University of Lisbon

AN&DR

Center of Technology and Engineering for Nuclear Projects (CITON)

Horia Hulubei, National Institute of Physics and Nuclear Engineering (IFIN-HH)

Institute for Nuclear Research – Pitesti (INR Pitesti)

Vinca Institute of Nuclear Sciences

Javys a.s.

Slovak University of Technology

ARAO

Geological Survey of Slovenia

Regional environmental center Country office (REC CO) Ljubljana

Slovenian National Building and Civil Engineering Institute

AITEMIN

Amphos XXI Consulting SL

CIEMAT

ENRESA

Fundación INASMET/ Fundación TECNALIA Research & Innovation

Universidad Politecnica de Madrid (UPM)

Kemakta Konsult AB

Microbial Analytics Sweden AB

NOVA FOU

SKB

SKB International AB

Stockholm University, Department of Physics

Studsvik Nuclear AB

AF-Consult Switzerland Ltd

Paul Scherrer Institute,Laboratory for Waste Management

Swiss Federal Institute of Technology (EPFL), Laboratory of Soil Mechanics (LMS)

MCM International

Nagra

COVRA

Deltares

TU-Delft

Netherlands Organisation for Applied Scientific Research, TNO

Nuclear Research and consultancy Group (NRG)

Resolution Resources International

Institute of Environmental Geochemistry NAS and MES of Ukraine

British Geological Survey

Galson Sciences Ltd

Geoenvironmental Research Centre, School of Engineering, Cardiff University

Loughborough University Chemistry Department

National Nuclear Laboratory

Quintessa Ltd

Research Centre for Radwaste & Decommissioning, the University of Manchester

RWM

The Birmingham Centre for Nuclear Education and Research

University of Sheffield

University of Strathclyde, Department of Civil Engineering

And some organisations...


Things to note:

• IGD-TP coordination with the European Commission.

• As written in the latest draft call for proposals to the Work Programme 2016-2017 of Euratom (related to research for geological repositories):

“The focus should be on topics of high priority and European added value that were raised in safety reviews and identified in

the SRA of IGD-TP.“

Research prioritization by IGD-TP.

IGD-TP SRA 2011: http://www.igdtp.eu/index.php/key-documents/doc_download/14-strategic-research-agenda

http://www.igdtp.eu/index.php/key-documents/doc_download/14-strategic-research-agenda





IGD-TP’s Strategic Research Agenda

- “dedicated to identifying the main RD&D issues that need a coordinated effort over the next years in order to reach the Vision 2025“

- “the SRA identifies the Key Topics of RD&D that have the greatest potential to support repository implementation through enhanced cooperation in Europe“


Key Topics defined by the IGD-TP:

1. Safety case

2. Waste forms and their behaviour

3. Technical feasibility and long-term performance of

repository components

4. Development strategy of the repository

5. Safety of construction and operations

6. Monitoring

7. Governance and stakeholder involvement



Each Key Topic contains a set or Topics.

Each Topic is prioritized as high, medium or low urgency.

Details on priorities are in the Deployment Plan.

(topic 4)



Some activities within the IGD-TP are “Cross-Cutting”:

• Dialogue with regulators

• Competence maintenance, Education and Training

• Knowledge Management

• Communication interfaces and other activities

supporting information exchange

Research prioritization by IGD-TP.Some activities within the IGD-TP are “Joint Activities”:

1. Waste forms and their behaviour2. Full scale demonstration of plugging & sealing3. Waste forms and their behaviour on C‐144. Monitoring of the environmental reference state5. Safety of construction and operations6. Confidence increase in the safety assessment codes ‐ materials

interactions7. Monitoring programme8. Safety case benchmarking9. Safety case peer review

10. Long‐term stability of bentonite in crystalline environments11. Sharing of knowledge on HLW container materials behaviour12. Adaptation and optimisation of the repository13. Communicating results from RD&D14. Competence, Maintenance, Education and Training15. Nuclear Knowledge Management16. WMOs Information Exchange Platforms


“All relevant stakeholders in Europe (industry, research centres, academia, technical safety

organisations, non‐ governmental organisations...) who endorse the IGD‐TP

Vision are welcome to join the IGD‐TP and contribute to the Exchange Forum (EF).“

About the SPIRE collaboration for spent fuel characterization.

Examples from IGD-TP’s Master Deployment Plan

High priority:1. Safety case: Refinement of the tools used in safety

assessment.

2. Waste forms: Rapid release fraction and matrix

dissolution of high burn-up fuels.

3. Technical feasibility: Long-term stability of bentonite in

crystalline environments.

6. Monitoring: Technologies and techniques


Examples from IGD-TP’s Master Deployment Plan

Medium priority:1. Safety case: Refinement of methods to make sensitivity

and uncertainty analyses.

2. Waste forms: High burn-up fuels and criticality.

4. Development strategy of the repository: Methodologies

for adaptation and optimisation during the operational

phase.


Identified needs for spent fuel characterization• Safety requirements on barriers in storage of spent

nuclear fuel need information on the spent nuclear fuel to be placed there:○ Decay heat○ Reactivity○ Gamma radiation○ Neutron radiation○ Nuclide inventory

• This need is common to both short term and long term storage issues.


Identified needs for spent fuel characterization• Measurement techniques to reliably determine decay

heat, reactivity, gamma- and neutron radiation from the nuclear fuel need to be established when the storage or repository begin operation.

• Models to be used for calculations or predictions must be validated and approved for use when the storage or repository begin operation.

• Uncertainties of all measured and calculated parameters must be quantified.

“Spent fuel characterization Program for the Implementation of (geological) REpositories” - SPIRE



SKB + UU:

• Decay heat measurements of fuel with long cooling time.

• Fuel characterization system’s integration in encapsulation facility (CLINK).

• Radiation impact on heat transfer in the geological storage.


SKB + E.ON + UU:

• Decay heat measurements of fuel with short cooling time.

• Radiation impact on heat transfer and dose in transport and in interim storage facilities.


SCK•CEN + UU + SKB:

● Development of:○ A Self-Interrogation Neutron Resonance

Densitometry prototype instrument.○ Medium resolution gamma rays spectroscopy using

Cadmium Zinc Telluride detectors.● Measurements on fresh MOX fuel in known conditions.● Measurements on spent fuel on-site (Clab).


UU + PSI + CCFE:

• Generalize the Total Monte Carlo scheme to all nuclear data uncertainties

• Calculate the decay heat in and burnup of fuel assemblies and estimate and minimize its uncertainties using the TMC methodology.

• Calculate criticality margins and associated uncertainties for both fuel storage and in deep repositories.

• Benchmark calculation results against both differential (e.g. IGISOL) and integral measurements.


LGI Consulting:

• Communication• Dissemination of results• Digital strategy and presence• Event management

DoE / NNSA / Los Alamos National Laboratory:

• At present: Scientific advisory body

Some on-going and plannedresearch projects.

FOLLOWS...

Copyright © 2015 SCK•CEN

SCK•CEN

● SCK•CEN goals for SPIRE

● Development of a Self-Interrogation Neutron Resonance Densitometry instrument for measurements on spent fuel

● Medium resolution gamma rays spectroscopy on spent fuel with CZT detectors

● Existing expertise

● Fork detector

● Beyond the Fork: ForkBall

● R&D on Innovative methods

● Spent Fuel Composition Libraries

● Detector modelling and validation


Self-Interrogation Neutron Resonance Desnitometry

● Self-Interrogation Neutron Resonance Densitometry (SINRD)

● Energy dependence of neutron cross-section is a unique signature

● Attenuation of the neutron flux is linked to 239Pu content

Rossa R., et al. A new approach for the application of the Self-Interrogation Neutron Resonance Densitometry to spent fuel verifications. Symposium on International Safeguards, Linking Strategy, Implementation and People, Vienna, Austria, IAEA, 2014, p. 270



● Self-Interrogation Neutron Resonance Densitometry (SINRD)

● How: fission chambers in the guide tubes of a PWR fuel assembly

● What: neutron flux in specific energy regions

● 239Pu fission chamber + Gd & Cd filters to select the 0.3 eV region

● 238U fission chamber to measure the fast neutron flux

Rossa R., et al. Optimization of the filters thickness for the SINRD technique applied to spent fuel verification.INMM 55th Annual Meeting Proceedings, Atlanta, GA, United States, 20-24 July 2014



● Main results from the initial study on SINRD

● Air and polyethylene to ensure the best conditions

● Avoid moderation within the fuel assembly

● Definition of the SINRD signature Rossa R., et al. Investigation of the Self-Interrogation Neutron Resonance Densitometry applied to spent fuel using Monte Carlo simulations.Annals of Nuclear Energy 75 (2015) 176–183


SINRD in SPIRE

● Development of a prototype

● Model calculations, design and building

● Measurements (SCK•CEN) of fresh MOX fuel with well-known

composition

● Model verification, methodology calibration

● Measurement (SCK•CEN) with a strong gamma/neutron sources

● Detector behaviour in realistic measurement conditions

● Measurements (SKB-CLAB) of well-known spent fuel.

● final validation of the method


Gamma rays spectroscopy on spent fuel with CZT detectors● Integration of CZT detector with other technologies (UU, SKB)

● Development of a prototype of the collimated CZT system

● Integration with equipment UU and SKB


Gamma rays spectroscopy on spent fuel with CZT detectors● Data analysis tool for the spectra with CZT detector

● Uncertainty assessment (CZT)

● Detector characterization with point sources

● Measurements in controlled conditions (e.g. dummy assemblies

with a well-known amount radionuclides in the fuel pins)

● Measurements with spent fuel and compare the data with

inventory calculations for final uncertainty assessment

NRG: For SPIRE

Generalize the Total Monte Carlo scheme to all nuclear data uncertainties:

• Cross section for all materials

• Angular distributions

• Thermal scattering

• Fission yields

Make these data and methodologies available to all partners

40A.J. Koning and D. Rochman, ``Towards sustainable nuclear energy: Putting nuclear physics to work'', Ann. Nuc. En. 35, p. 2024-2030 (2008).

TENDL and Total Monte Carlo

1000 Simulations: Depletion and reactor-codes

Experimental data for calibration

Nuclear model parameters: many acceptable

Nuclear models: nuclear interaction-TALYS

~1000 acceptable ND libraries

Applications: Reactor safety, fuel cycle, inventory, material damages

0.98 1.00 1.02 1.05 1.07

20

40

60

80

100

Select Best ND libraryTENDL

Check for co-variance between all the libraries

Observables: CS, FY, Angular distribution

with cov-matrix

Total Monte Carlo: uncertainty propagation

av

rv

Total Monte Carlo U.Q. • Straight forward and transparent treatment of the

uncertainty propagation • Bias free uncertainty propagation, e.g. no

linearization.

• Non Gaussian behavior in input and output can be modelled.

• More complete U.Q., e.g. all ND

Looping over nuclear science

- Use (extremely) robust software- Store all human intelligence in input files and scripts- Rely on reproducibility and quality assurance

Road to success:

Feedback, sensitivity, uncertainty propagation, …..

Total Monte Carlo

TMC examplePWR burn-up calculations

D. Rochman, A.J. Koning and D. da Cruz, ``Propagation of 235,236,238U and 239Pu nuclear data uncertainties for a typical PWR fuel element'', Nuclear Technology 179, no. 3, 323-338 (2012).

Phenomenological data for simulation

• Nuclear simulation codes (MCNP, EASY, etc.) do not contain all physics of particle interaction (cross section, angular/energy emitted spectra.) but read from nuclear data tables

• Knowledge of nuclear interactions derived from careful and expensive experiments + sophisticated modelling

• Decades of effort has resulted in relatively reliable information for simulation of LWRs operation (not dismantlement) and other specific applications – using tiny fraction of nuclides/reactions

• Simulation of advanced reactors, geological storage will require substantially greater library with much more detail than simple σ(E)

47

EASY-II roadmap1. FISPACT-2007+ & EAF-2010 in EAF format processed by SAFEPAQ-II ☑ 08/2010

2. FISPACT-II(11) & EAF-2010 in EAF format processed by SAFEPAQ-II ☑ 01/2011

3. FISPACT-II(11) & EAF-2010 + CALENDF PT’s ssf method, ENDF’s format and processing framework ☑ 09/2011

4. EASY-II(12) = FISPACT-II(12) & EAF’s and TENDL-2011 ENDF’s libraries processed by NJOY, PREPRO & CALENDF ☑ 03/2012

5. EASY-II(13) = FISPACT-II & EAF’s and TENDL’s V&V libraries processed by NJOY, PREPRO & CALENDF ☑ 06/2013

6. EASY-II(14) = FISPACT-II & EAF’s, TENDL’s, ENDF’s libraries, automated V&V processes ☑ 07/2014

7. EASY-II(15) = FISPACT-II & TENDL’s, ENDF’s libraries, automated V&V processes 06/2015

Vigilant, thorough V&V stepped approach

Closing the technological loop

• The Total Monte Carlo (TMC) methodology uses direct feedback from simulation to physical inputs

• TMC provides truly remarkable uncertainty analysis based upon simulation outputs – where legacy provides little/none

• TMC is as good as the simulation capability. The marriage of TENDL with EASY provides the most robust methodology

By bringing the disjoint nuclear data links, from evaluation to application, into a technologically-driven closed system we can provide complete, robust data

superior to any legacy system

Current focus @ Uppsala

• Improved calibration of TENDL using both integral and differential data.

• UQ for fast and thermal reactor systems.

• Angular distributions– Uncertainties not well

evaluated 50

Measurement of independent fission yields in thermal and fast neutron spectra – IGISOL, Finland

To be done @ Uppsala

• Marriage between TALYS + GEF. – GEF is the best currently available nuclear fission model. GEF

will be the basis of future nuclear data evaluations by NEA/OECD within JEFF

• Calculate the decay heat in and burn-up of the fuel assemblies and estimate and minimize its uncertainties using the TMC methodology. Benchmark the results against both differential measurement (e.g. IGISOL) and integral measurement.

• Calculate criticality margins and associated uncertainties for both fuel storage and in deep repositories. Benchmark the results against both differential measurement (e.g. IGISOL) and integral measurement.

51

Relations

UU, NRG, CCFE, (PSI)

TENDL,TMC, EASYII

SPIRE collaboration

Simulations and experiments for repositories

Nuclear data, code systems and U.Q.

Integral data for calibration and validation

E.ONs participation in SPIRE

• Uncertainties in neutron/ gamma dose and uncertainties of the decay heat are important factors for the safe and economical storage of spent nuclear fuel in interim storage facilities and in geological repositories.

• The uncertainties may be comparatively small on a fuel assembly basis but for the storage of hundreds and thousands of fuel assemblies the financial consequences are significant.

E.ONs participation in SPIRE:Motivation

• Minimization of the source term uncertainties, i.e:

• Accomplish source term uncertainty calculations for spent nuclear fuel given the latest covariance data from data libraries

• Second major aim is to adapt the latest technology from non-proliferation surveillance in order to significantly reduce the measurement uncertainties of the gamma and neutron dose and of the decay heat

E.ONs participation in SPIRE:Objective

• Path 1: Identification of gaps in the knowledge of the microscopic cross sections and nuclide yields and to fill these gaps with more data in order to reduce the microscopic data uncertainties.

• Path 2: Development of measurement equipment which can cut the current measurement uncertainties at least by a factor of two.

• These two routes are mutually reinforcing because• the better the measurements are, the better the knowledge gaps on the

microscopic data can be identified, and• the smaller the microscopic uncertainties are, the easier it is to design high

precision measurements.

E.ONs participation in SPIRE:Proposed approach

No Description1 Methodology development and demonstration of taking into account the

following uncertainties in source term calculation:- cross section uncertainties- nuclide yield uncertainties- power history uncertainties (i.e. burnup)- fuel assembly manufacturing tolerances

2 Improvement of measurement devices for decay heat, neutron & gamma dose and reduction of current uncertainties by at least a factor of two.

3 Measurement campaign at CLAB and/ or at NPP site to increase data base. Sample of fuel assemblies should cover shutdown cooling period between about 3 and 20 years. Repetitive measurement of homologous fuel assemblies with same, nominal burnup.

4 Evaluation of results of uncertainty analysis & measurement uncertainties to derive a final uncertainty of decay heat, n- and gamma dose.

E.ONs participation in SPIRE:Proposed focus

• Test and use the developed measurement equipment in one of its Nuclear Power Plants in order to determine the source terms on a suitable set of selected fuel assemblies

• Provide reactor power histories of selected fuel assemblies as input for theoretical calculations.

• This on-site measurement has the advantage that both fuel assemblies with a relatively short time after discharge and homologous pairs of fuel assemblies can be included into the database.

E.ONs participation in SPIRE:Potential contribution

SKB / DoE / Euratom / UU Collaboration

• Research effort to determine the capability of non-destructive assay (NDA) techniques for spent fuel.

• Partial defect detection• Heat quantification• Assembly operational parameters (IE, BU, CT)• Pu mass• Reactivity determination

• To meet the combined needs of … • the safeguards community• the operator (SKB)


Experimental signatures measured at Clab from…

• Spectral resolved gammas (HPGe and LaBr3).

• Time correlated neutrons (Differential Die-away Self Interrogation).

• Time-varying and continuous active neutron interrogation (Differential Die-Away).

• An approximation of Californium Interrogation Prompt Neutron (CIPN).

• Total neutron and total gamma fluxes (FORK Detector).

• Total decay heat (assembly length calorimeter).

• Possibly also Cerenkov light emission (Digital Cerenkov Viewing Device).

“On-going” spent fuel measurements at Clab:• Calorimetric measurements of decay heat.• Passive gamma measurements (HPGe).

Measurements currently planned to be performed at Clab:• Passive neutron measurements (FORK).• Passive gamma measurements (HPGe, LaBr3).• Differential die-away self interrogation measurements

(DDSI).• Differential die-away measurements (DDA).


• Partial defect detection• Heat quantification• Assembly operational parameters (IE, BU, CT)• Pu mass• Reactivity determination


Determined using...• the experimental signatures• data mining (“analytic solver”)

S. Tobin et al, “Experimental and Analytical Plans for the Non-destructive Assay System of the Swedish Encapsulation and Repository Facilities”,IAEA Symposium on International Safeguards: Linking Strategy, Implementation and People. 2014: https://www.iaea.org/safeguards/symposium/2014/home/eproceedings/sg2014-papers/000238.pdf

https://www.iaea.org/safeguards/symposium/2014/home/eproceedings/sg2014-papers/000238.pdf

Summary

You have seen and heard about:

• The IGD-TP and it’s role in Europe.

• How IGD-TP prioritizes research related to deep

geological storage.

• About the SPIRE collaboration for spent fuel

characterization and.

• Some on-going and planned research projects related

to spent nuclear fuel characterization for deep

geological storage.

Thank you for your attention!

For more information, please contact:

Peter JanssonUppsala UniversityDepartment of Physics and AstronomyDivision of Applied Nuclear Physics

Phone: +46-(0)18-4715841LinkedIn: https://se.linkedin.com/in/drpeterjansson

https://se.linkedin.com/in/drpeterjansson