OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES - NCSP

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               OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES
               NCSP TPR MEETING, 2021 FEBRUARY THE 23RD
               DES (DIRECTION OF ENERGIES) SERMA (SACLAY)-SPRC (CADARACHE)
               DES/ISAS/DM2S – DES/IRESNE/DER
               C Carmouze, M Laget, YK Lee, D Noyelles, JC Trama

               Commissariat à l’énergie atomique et aux énergies alternatives - www.cea.fr
Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES
OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES - NCSP
2021 NCSP TPR MEETING : CEA participants

    Coralie Carmouze : Cadarache (SPRC, CEA expert on neutronics
       applied to criticality-safety and nuclear fuel cycle)

    Michael Laget : Saclay (SERMA, CEA criticality safety expert
       team, criticality accident expert)

    Yi-Kang Lee  : Saclay (SERMA, TRIPOLI Monte Carlo team,
       benchmarking expert)

    David Noyelles : Saclay (SERMA, CEA criticality safety expert
       team, criticality safety expert)

    Jean-Christophe Trama : Saclay (SERMA, criticality safety and
       radiation shielding advanced users group manager)

Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES   2
OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES - NCSP
CEA CRITICALITY SAFETY ORGANISATION

               Commissariat à l’énergie atomique et aux énergies alternatives - www.cea.fr
Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES   3
OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES - NCSP
CEA : Alternative Energies and Atomic Energy Commission

             A key player in research, development and innovation in four main areas:
             defense and security (CEA DAM), low carbon energies (CEA DES nuclear and
             renewable energies), technological research for industry (CEA DRT), fundamental
             research in the physical sciences and life sciences (CEA DRF). 20181 employees, 9
             research centers, 5 billion euros budget (2019). cea.fr/english

Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES   4
OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES - NCSP
Neutronics @ CEA DES : reactor physics, fuel cycle, criticality-
                               safety, radiation protection and shielding
                                     From R&D to nuclear facilities
  Two R&D units, SERMA @ Saclay and SPRC @ Cadarache, totaling 140 permanent staff + 40 PhD + 50 interns/yr.

                                                                                   https://www.cea.fr/energies/tripoli-4
                                                                                                                                 For criticality safety, CEA is
                                                                                                                                       closely working
                                                                     Transport                                                   with IRSN on the CRISTAL*
                                                                       Code                                                            criticality-safety
                                                                    Development                                                  package, embedding codes
                                                                                                CRISTAL
                                                                                                                                   from both institutions

                                    Nuclear Data
                         JEFF 3                                                                    Calculation
                                     Evaluation,
                                                                                                   Sequences
                                    Validation &
                                                                                                    definition
                                     Processing                                                                          Fast reactors   RJH
              GALILEE                                               Neutronics
                                                                    @ CEA DES                                                                          Transport cask

                                                                                                                            SMR          EPR

    CEA DES or Partners                           Advanced
                                                                                      Verification
                                                 User Groups,
     Nuclear Facilities                                                               Validation &
                                                   Criticality
                                                                                      Uncertainty
                                                 Safety Expert
                                                                                     Quantification
                                                     Team

                                                                                    *www.cristal-package.org // *https://www.oecd-nea.org/tools/abstract/detail/nea-1903

Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES                             5
OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES - NCSP
CEA DES as a nuclear operator : criticality safety organisation

                                                                                   CEA–MARCOULE                              CEA–PARIS SACLAY
     CEA DES as a Nuclear
     operator : ~30 facilities                                   CONTROL LINE – LOCAL
                                                                  CS :                                                           CS
     handling fissile material                                                                                                   CCE
     on Saclay, Marcoule and                                      Criticality Specialist
                                                                                                                                 QCE1,
     Cadarache :                                                         SUPPORT LINE – LOCAL                                    QCE2...
     experimental reactors,                                              CCE :
     dry storages, pools,                                                Centre Criticality Engineer
     shielded cells, glovebox,                                                   Facility #1                 Facility #2
     storage facilities, waste                                                                               QCE
                                                                 OPERATIONAL LINE
     management                                                                                                               CEA–CADARACHE
                                                                 QCE :                                       Facility #3
                                                                 Qualified Criticality Engineer              QCE
                                                                                                                                 CS
                                                                                                                                 CCE
                                                                   Facility #x                 Facility #5   Facility #4
                                                                                                                                 QCE1,
                                                                  QCE                          QCE           QCE
                                                                                                                                 QCE2...
                  Saclay

                        Marcoule                             SUPPORT LINE – CENTRAL
                        Cadarache                                                               Criticality Safety Expert Team (CST)
                                                                                                Saclay
                                                                          CSEG : Criticality Safety Expert Group

                   People involved : CST (Saclay) 8 ; CCE 4 ; QCE : ~30 and CS 3
Commissariat à l’énergie atomique et aux énergies alternatives    NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES      6
OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES - NCSP
EXAMPLES OF CEA DES R&D IN CRITICALITY SAFETY

               Commissariat à l’énergie atomique et aux énergies alternatives - www.cea.fr
Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES   7
CEA DES R&D in criticality-safety example 1 (CST, SERMA, Saclay)
                  early detection of criticality accident through neutron noise analysis

   •   Criticality accidents are monitored by Criticality Accident
       Alarm System (CAAS), basically by monitoring neutron
       counts on sensors
   •   Is it possible to have an earlier warning based on the
       monitoring of statistics of neutron arrival times on the
       sensors ?
   •   Feasibility of neutron noise analysis on analog TRIPOLI4®
       simulations: demonstrated on SILENE experimental results
   •   Different analysis techniques implemented : Feynman-α,
       Rossi- α, uncertainties by bootstrap method                                                        2nd and 3rd order Feynman
                                                                                                          parameters, simulated through a
   •   Preliminary evaluation of different fission models (FREYA,                                         sequentiaal binning of events
       FIFRELIN)
   Next step: Parametric studies on the sensitivity and potential
   range of application of the method
   Further: define an experimental setup (probes, electronics) to
   evaluate the concept on a critical assembly

                                                                                                              8

                                                                           2nd and  3rdorder Feynman parameters,
                                                                           as a function of double and triple correlated detections

Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES       8
CEA DES R&D in criticality-safety example 2 (TRIPOLI Team, SERMA,
                           Saclay) sensitivity analysis tools for k-eigenvalue

        TRIPOLI-4®: continuous-energy Monte Carlo particle transport code developed by
         CEA, Saclay, production-level code for CEA and EDF, and R&D tool
        Reference calculation sequence for CRISTAL
        Generic features: https://www.cea.fr/energies/tripoli-4
        V&V based on international benchmarks (including ICSBEP) and CEA proprietary
         experimental facilities
          Examples of sensitivity analysis tools for k-eigenvalue
                - Reactivity perturbations: variations in material compositions, cross sections, and fission
                  neutron multiplicities
                - Sensivity coefficients of k-eigenvalues to nuclear data: cross sections, fission spectra,
                  scattering laws and fission neutron multiplicities
                - Uncertainty propagation: COMAC covariance matrices

                                                                                                              9

                                                                                                          Reactivity effect due to variations in the
                                                                                                          density of an inner shell for GODIVA
                                                                                                          Terranova et al., ANE 121, 335-349 (2018).
Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES          9
CEA DES R&D in Criticality-Safety Example 3 (SPRC, Cadarache)
                  Nuclear Data evaluation, processing & benchmark calc. e.g. Thermal Scattering Laws
                           Experiment - Evaluation                                                                    Processing

                                                                                                                 Processing with the LEAPR and
                                                                                                                  THERMR modules of NJOY
    Phonon density of states JEFF-3.3
                                                        Experimental validation with ILL data
        (Bariloche, Argentina)
                                                                (Grenoble, France)

 Integral benchmark calculation e.g. OCDE/NEA-WPNCS-SG3

                                                                                                               Covariance matrix generated with
                                                                                                                      the CONRAD code
                                                                                                      Effect and Uncertainties of H in Ice Thermal
                                                                                                      Scattering Laws on neutron multiplication factor
                                                                                                      for PWR Fuel criticality capplications. ICNC 2019,
Sensitivity Coefficient & Uncertainty propagation (TRIPOLI-4)
                                                                                                      M. Tiphine, C. Carmouze, G. Noguere et all.
 Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES             10
CEA DES R&D in Criticality-Safety Example 4 (SPRC, Cadarache)
                    From codes VV-UQ* to industrial application e.g Burnup Credit

                           Depletion calculations                                Criticality calculations
                                                                                                                   keff
     CEAV512 Nuclear Data Libraries based on JEFF-311 Evaluation

       Codes development : APOLLO2, TRIPOLI-4, DARWIN2 (@CEA Saclay)
       Nuclear data processing

                                                                                                                                        Dedicated experimental programs
       Dedicated calculation sequence definition & VV-UQ process
        DARWIN depletion calculation package (CEA, EDF, Framatome, Orano)
        VV-UQ based on French Post Irradiated Experiment
        CRISTAL criticality-safety package (CEA, IRSN, Orano, Framatome)
        VV-UQ based on international benchmarks (including ICSBEP)
        & Nuclear Data validation : Oscillations Experiments in the CEA MINERVE reactor
        for the validation of the BUC Fission Products capture cross-sections
       *Verification, Validation and Uncertainty Quantification

       BUC integrated method to take calculation bias
       & bias uncertainties into account in industrial                                                        11

       calculations
        Burnup Credit application for transport cask using french expriments. PHYSOR 2014, M. Tardy et. all.
Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES                                     11
POSSIBLE COLLABORATION WITH THE US DOE NCS PROGRAM

               Commissariat à l’énergie atomique et aux énergies alternatives - www.cea.fr
Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES   12
criticality safety training :
                                                  the lack of hands-on training at CEA

The example of the CCE training course
  A very high level training course under the responsibility of INSTN (National
   Institute for Nuclear Science and Technology)
  1 session every 2 years, 7 one-week sessions including a one-week internship
   with a CCE (from any French licensee)
  2 exams, 1 internship report, 1 oral exam to an expert committee
  Mandatory to become CCE of CEA or any other licensee
  Trainers are recognized experts of the domain (from IRSN, CEA -including the
   CST-, Orano…)
  See backup slides for the detailed content of the training
  But since the shut down of the VALDUC facilities in 2014, after years of
   fruitful collaboration between CEA, US DOE and IRSN : there has been no
   possibility for the CEA personnel to have hands-on criticality safety training
   on experimental facilities.
  We would be very interested to study the possibilities for CEA personnel to
   be trained in the US
  https://ncsp.llnl.gov/training.php

Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES   13
Possible collaboration with the US DOE Nuclear Criticality Safety
                    Program

              Hands-on training session : CEA personnel                                                       trained in
                  partnership with the NCS Program

              Early detection of criticality accident : theoretical work,
                  comparisons of simulations, definition of an experiment

              Monte Carlo and Nuclear Data benchmarking       :
                  independent evaluation of US experiments (ICSBEP, Post-
                  Irradiated Experiments) - comparison with the last JEFF
                  evaluation

Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES   14
THANK YOU FOR YOUR ATTENTION

               Commissariat à l’énergie atomique et aux énergies alternatives - www.cea.fr
Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES   15
BACKUP SLIDES

               Commissariat à l’énergie atomique et aux énergies alternatives - www.cea.fr
Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES   16
Neutronics @ CEA DES : reactor physics, fuel cycle, criticality-
                                  safety, radiation protection and shielding
                                        From R&D to nuclear facilities
             Two R&D units, SERMA @ Saclay and SPRC @ Cadarache, totaling 140
             permanent staff + 40 PhD + 50 interns/yr.
             Together they are in charge of a whole set of modeling and simulation tools for
             neutronics : nuclear data evaluation and processing, transport codes
             development, calculation sequences edition, verification, validation and
             uncertainty analysis. Advanced user groups are in charge of specific nuclear
             analysis in reactor physics, fuel cycle, criticality-safety, radiation shielding and
             nuclear instrumentation for CEA and its partners, at all stages of nuclear facilities
             life cycle (from design to D&D).
             A dedicated team to support the CEA nuclear facilities with regards to criticality
             safety : the CEA Criticality Safety Expert Team (CST)
             Some signature codes and sequences : the APOLLO cell and lattice code, the
             TRIPOLI Monte Carlo code (https://www.cea.fr/energies/tripoli-4), CONRAD for
             nuclear data evaluation and GALILEE for their processing, the REL calculation
             sequence for PWR core physics, all are production level
             For criticality safety, CEA is closely working with IRSN on the CRISTAL criticality
             safety package, embedding codes from both institutions.
             www.cristal-package.org and NEA-1903 package
              https://www.oecd-nea.org/tools/abstract/detail/nea-1903/
Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES   17
criticality safety training

CCE training course - content
         Introduction to criticality hazard                                                 Calculations
         Organization in France                                                    Module 3 Codes and tools of Cristal package
         Introduction to neutron physics                                                    Practical exercices
  Module Nuclear physics
    1    Chain reactions, neutron balance                                                   Criticality safety in tranportation
         Boltzmann Equation                                                                 Introduction to nuclear fuel cycle
         Practical use of simplified theory                                                 Fissile material storage
         Methods to prevent criticality risks                                               Enrichment and conversion
         manipulate the order of magnitude                                                  UOX Fuel fabrication
         dilution law and isopiestic                                                        Reprocessing Plant
                                                                                   Module 4
         using curves and control modes                                                     Mass control
  Module guidances and standards                                                            MOX Fuel Fabrication
    2    codes validations exp. benchmarks                                                  Practical examples
         methods of control                                                                 Fuel Storage
         safety margins                                                                     Dismantling
         NCS analysis and demonstrations                                                    Events : Feed back and lessons

Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES   18
criticality safety training

CCE training course - content
         Introduction to criticality accidents
         History of criticality accidents                                                        Interaction CCE and calculation teams
         Experimental machines                 Module 6                                          Practical cases
         Practical exercices                                                                     Human factors
         Accident calculs codes                Module 7                                          Internship with a CCE
         Practical case on a reactor
         Numerical case                                                                          Conversations with CCE
         CAAS                                  Module 8                                          Exam
         Intervention and examples                                                               Jury
Module 5
         Radiation in case of accidents
         Visit of measurement laboratory
         Medical aspects
         Emergency prepardnessmanagement
         Visit of the crisis center of IRSN
         Regulatory aspect (accident)
         Simple formulas to estimate fisson number
         CCE in case of a crisis
         Practical case
Commissariat à l’énergie atomique et aux énergies alternatives   NCSP TPR MEETING : OVERVIEW OF CEA DES CRITICALITY SAFETY ACTIVITIES   19
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