Akademik Sunum

Sıra	DOSYA ADI	Format	Bağlantı
01.	Compilation Computations Files Perturbation	pptx	Sunumu İndir Sunuyu İndir Sunumu İndir

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© 2016 Organisation for Economic Co-operation and DevelopmentBenchmarking and Validation Activities within JEFF Project O. CabellosNEA Data Bankoscar.cabellos@oecd.orgICTP-IAEA Workshop on the“Evaluation of Nuclear Reaction Data for Applications”October 9-13, 2017. Trieste, Italy

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© 2016 Organisation for Economic Co-operation and Development The challenge for any nuclear data evaluation project is: To periodically release a revised, fully consistent and complete library, with all nuclear data needed + covariances To ensure that it is robust and reliable for a variety of applications Benchmarking activities play an important role!! The aim of this presentation is to present the activities carried out by the new JEFF Benchmarking and Validation Working Group, and to describe the role of the NEA Data Bank in this context This presentation will also review the status of preliminary benchmarking for the next JEFF-3.3 candidate cross-section filesObjective

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© 2016 Organisation for Economic Co-operation and DevelopmentOutline1. NEA Data Bank: Tools and Databases 1.1 DICE1.2 NDaST1.3 NDEC2. JEFF B&V WG3. Benchmarking and Validation of JEFF-3.33.1 General validation and Activation Benchmarks3.2 Criticality benchmarks3.3 Shielding and benchmarks for fusion application3.4 Burnup Benchmarks3.5 Reactor benchmarks and new designs3.6 Covariance verification4. ConclusionReferences

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© 2016 Organisation for Economic Co-operation and Development1. NEA Data Bank: Tools and Databases Fig.1 NEA Data Bank tools and databases. JEFF Working Groups on Nuclear Data activities on Benchmarking & Validation (B&V), Processing & Verification (P&V) and Evaluation are shownNEA Data Bank Services Secretariat activities Technical services: Consistency checks Conversion to formats Testing/verification Benchmarking (e.g. ICSBEP, …. Web/Compilation library Feedbacks New tool NDEC (Nuclear Data Evaluated Cycle).

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© 2016 Organisation for Economic Co-operation and Development© 2015 Organisation for Econo o-operation and Development 5https://www.oecd-nea.org/science/wpncs/icsbep/dice.htmlICSBEP (International Handbook of Evaluated Criticality Safety Benchmark Experiments Project) is a project whose objective is:- To compile critical and subcritical benchmark experiment data into a standardised format that allows criticality safety analysis- To easily use the data to validate calculation tools and cross-section libraries.DICE is the Database for ICSBEP, provided with a searching tool in JAVA• What? • Features– Online info P/T/M– Databases/Format– Search– Comparing data– Computations• Users– Evaluators– Application• Future developments– Databases– Formats– Plotting– Computations1.1 DICE

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© 2016 Organisation for Economic Co-operation and Development© 2015 Organisation for Econo o-operation and Development 6• What? • Features– Online info P/T/M– Databases/Format– Search– Comparing data– Computations• Users– Evaluators– Application• Future developments– Databases– Formats– Plotting– Computations1.1 DICEPlotting sensitivity profilesAccessing benchmark PDFs for reading

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© 2016 Organisation for Economic Co-operation and Development© 2015 Organisation for Econo o-operation and Development 7• What? • Features– Online info P/T/M– Databases/Format– Search– Comparing data– Computations• Users– Evaluators– Application• Future developments– Databases– Formats– Plotting– Computations1.1 DICEHandbook EditionNumber ofUnique Cases Sources2012 727 TSUNAMI1D+TSUNAMI3D [VALID]+MMK-KENO2013 3575 Previous +Non VALID cases SCALE6.0 from Balance Inputs2014 4011 Previous + MCNP6 + SCALE6.2BClutch THERM INTER FAST MIXEDPU 525/608 4/10 114/121 9/9HEU 664/895 21/32 383/403 75/84IEU 142/180 5/21 31/43 7/23LEU 1424/1612 0/0 1/1 5/5U233 186/197 29/29 8/10 8/8MIX 323/436 2/7 40/67 1/26SPEC 0/0 0/0 4/20 0/0Sensitivity Data…. Recently much improved!

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© 2016 Organisation for Economic Co-operation and Development© 2015 Organisation for Econo o-operation and Development 8• What? • Features– Online info P/T/M– Databases/Format– Search– Comparing data– Computations• Users– Evaluators– Application• Future developments– Databases– Formats– Plotting– Computations1.1 DICESet ThresholdSearching experimental benchmarks using different fields:− e.g. Sensitivities− 3-g search, full 238 Group SDF’s are stored for plotting and computations

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© 2016 Organisation for Economic Co-operation and Development© 2015 Organisation for Econo o-operation and Development 9• What? • Features– Online info P/T/M– Databases/Format– Search– Comparing data– Computations• Users– Evaluators– Application• Future developments– Databases– Formats– Plotting– Computations1.1 DICE Ex: DICE Plotting of Be Sensitivity > 0.005 for HMFCan also read as 100 pcm/1% change in ∑Be Sensitivity

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© 2016 Organisation for Economic Co-operation and Development© 2015 Organisation for Econo o-operation and Development 10• What? • Features– Online info P/T/M– Databases/Format– Search– Comparing data– Computations• Users– Evaluators– Application• Future developments– Databases– Formats– Plotting– Computations1.1 DICEElement or IsotopeThreshold(pcm/%∑)Benchmark CasesDeuterium >100 HST001(1-2), HST004(3-6),HST020(1-5), HCI006(6), HCT017(1-9), HCM002(7,10,11,20), LMT001(1),LMT002(1-12), LMT015(1-22)Fe <-100 >100PMF015(1),PMF026(1),PMF028(1),PMI002(1),HMF021(1),HMF085(3),HMI001(1), IMF005(1),MMI003(1),SPECMF014(1),HMI001(1)Cu >100 PMF013(1),HMF072(1-3),HMF073(1),HMF085(1-2),HMI006(1-4),IMF020(2,4-5)Gd157 <-100 PST034(3-6),HST014(3),HST016(2,3),LCT005(3,4,9-11), LCT052(1-6),MST006(4-6),MST007(3-7),MMCT004(4-6)W <-50 and >50HMF060(1),HMF067(1-2),HMF070(1-3),IMF014(2),PMF005(1),HMF003(8-11), HMF049(3),HMF050(1),HMF084(14),HMF085(6)Basic statistics: Table of Benchmarks with sensitivity above Threshold

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© 2016 Organisation for Economic Co-operation and Development© 2015 Organisation for Econo o-operation and Development 11http://www.oecd-nea.org/ndast/NDaST (Nuclear Data Sensitivity Tool) brings together the existing capabilities of both DICE and JANIS, whose main objective is :- to quickly propagate the impact of changes in nuclear data cross sections and nuclear data covariances to benchmarks• What? • Features– Online info P/T/M– Databases/Format– Search– Comparing data– Computations• Users– Evaluators– Application• Future developments– Databases– Formats– Plotting– Computations1.2 NDaST

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© 2016 Organisation for Economic Co-operation and Development© 2015 Organisation for Econo o-operation and Development 12NDaST (Nuclear Data Sensitivity Tool) An open web-based JAVA tool (on-line) Enable rapid scoping of changes to nuclear data and to propagate nuclear covariance data uncertainties Ability to determine individual reaction breakdowns and to simply analyse competing effect• What? • Features– Online info P/T/M– Databases/Format– Search– Comparing data– Computations• Users– Evaluators– Application• Future developments– Databases– Formats– Plotting– ComputationsCurrent Status• Released for beta-testing- Collect user feedback to inform development plans and assist bug-fixing- Appraise user-friendliness and simplicity• Exploring uses and limitations- Range of applicability: Linearity- Schemes for energy integration and group collapse: SCALE 238 group energy structure- Number of perturbations (not all are loaded into database)1.2 NDaST

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© 2016 Organisation for Economic Co-operation and Development© 2015 Organisation for Econo o-operation and Development 13• What? • Features– Online info P/T/M– Databases/Format– Search– Comparing data– Computations• Users– Evaluators– Application• Future developments– Databases– Formats– Plotting– ComputationsSensitivities Panel: Data needs to be added in order to provide the cases for which the subsequent calculations will be carried out1.2 NDaST

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© 2016 Organisation for Economic Co-operation and Development© 2015 Organisation for Econo o-operation and Development 14• What? • Features– Online info P/T/M– Databases/Format– Search– Comparing data– Computations• Users– Evaluators– Application• Future developments– Databases– Formats– Plotting– ComputationsCurrent Databases: - Experimental benchmarks in DICE and IDAT(useful only when benchmarks have sensitivity profiles)- Nuclear data covariance in JANIS databaseFormats- Sensitivity data: SCALE, ABBN formats- Covariance data: ENDF-6, BOXER and COVERX (SCALE6.1)“Add selected search results to your benchmark set” at bottom left of the panelHMF-008-0011.2 NDaST

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© 2016 Organisation for Economic Co-operation and Development© 2015 Organisation for Econo o-operation and Development 15• What? • Features– Online info P/T/M– Databases/Format– Search– Comparing data– Computations• Users– Evaluators– Application• Future developments– Databases– Formats– Plotting– ComputationsPerturbation Panel NDasT performs matrix multiplication for calculating keff perturbations and keff uncertainties Plotting capability: - experimental keff + uncertainty- calculated keff + perturbation (including breakdown) + uncertainty Save status (benchm./perturb./covariance selections) in XML format file Addition of Reactions and Perturbations: Computation of Ratios in JANIS1.2 NDaST

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© 2016 Organisation for Economic Co-operation and Development© 2015 Organisation for Econo o-operation and Development 17• What? • Features– Online info P/T/M– Databases/Format– Search– Comparing data– Computations• Users– Evaluators– Application• Future developments– Databases– Formats– Plotting– ComputationsCovariances Panel~920 pcm~580 pcmOnly inelastic ENDF/B-VII.1 All ENDF/B-VII.1 covariances• Dk/k perturbation (red)• Dk/k benchmark uncertainty (blue)• Dk/k based on the ENDF7.1 covariance file (green)Search covariances and press ‘ok’:- JANIS Database - Format: ENDF, BOXERGo! and Output Results Panel 1.2 NDaST

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© 2016 Organisation for Economic Co-operation and Development1) Use DICE to see results of Direct PerturbationLoad keff data, view in “Trend Plots” and compare different results from two different calculations2) Use NDaST to see the effect of switching from JEFF-3.1.1 to ENDF/B-VII.1 Comparison with the “Direct Perturbation” method.The natC(n,g) cross section in ENDF/B-VII.1 and JEFF-3.1.1 and its impact on results of criticality calculations(see JEFDOC-1456)Application to LEU-COMP-THERM-060 RBMK reactor criticality benchmarkExercise – 1.

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© 2016 Organisation for Economic Co-operation and Development1) Use JANIS to create a new Baseo U235 and Pu239 JEFF-33T4 files (HENDF+BOXER)2) Use DICE to see keff values of a Validation Suiteo NEA calculations3) Use NDaST to calculate the UncertaintiesVisualization C/E + Benchmark uncertainty + ND uncertaintyVisualization ICSBEP Mosteller’s Suite keff values(see JEFDOC-1843)Uncertainty Propagation Analysis and Comparison(see JEFDOC-1850)Exercise – 2.

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© 2016 Organisation for Economic Co-operation and Development1.3 NDEC NEA/DB working on: “Nuclear Data Evaluation Cycle” (NDEC) Systematized workflow of data for the verification, processing, differential validation and integral benchmarking of evaluated nuclear data Developed, hosted, maintained and co-ordinated at the NEA/DB by the DB Built around already existing NEA tools (JANIS, ICSBEP/DICE, etc…) and implementing new ones, in a collaborative working environment Sub-versioning system to keep traceability of submitted files Facilitate the implementation of a more project-managed approach for the production and final Q&A of nuclear data libraries (JEFF, CIELO,…) Fig 2. Nuclear Data Evaluation Cycle (NDEC) platform

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© 2016 Organisation for Economic Co-operation and Development2 JEFF B&V WG JEFF-3.2 General Purpose File (released in March 2014) JEFF-3.2 Special Purpose Files to be released Decay Data update in 2016 Fission Yields (will integrate FY data from GEF/GEFY) update in 2016 JEFF-3.3 (2017) Further improvements and extensions for fission (fast reactors, transmutation) and fusion (e.g. IFMIF) Integrate multiple contributions from WPEC SGs (CIELO…), EC-sponsored initiatives (e.g. CHANDA, H2020) Tested with NDEC JEFF-4: - 4 C’s : Complete, Consistent, with Credible Covariances Next generation Nuclear Data will be high quality data which can be reliably used in uncertainty assessment studiesFig 3. New mandate of the JEFF project (2015-2018)https://www.oecd-nea.org/dbdata/jeff/C. De Saint Jean (France)

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© 2016 Organisation for Economic Co-operation and Development3 Benchmarking and Validation of JEFF-3.33.1 General validation and Activation Benchmarks3.2 Criticality benchmarks3.3 Shielding and benchmarks for fusion application3.4 Burnup Benchmarks3.5 Reactor benchmarks and new designs3.6 Covariance validation

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© 2016 Organisation for Economic Co-operation and Development3.1 General Validation & Activation Benchmarks Decay data in activation experiments Fission decay heat (pulse and finite irradiations) FNS(JAEA) and FNG(ENEA) experiments M. Fleming, EFFDOC-1293 (2016) General-purpose verification and validation Checks on RI, thermal Maxw., systematics 14 MeV,…M. Fleming, JEF/DOC-1723 (2015)Table 1. Rel. error(in s) integral resonancesIso Reac. EXFOR(C-E)/DEENDF/B-VII.1JEFF-3.2 JENDL-4.0-2TENDL-2014Ti50 (n,g) V1001.169 1 392 1 1Cf253 (n,g) V1002.703 215 215 215 -3Ti50 (n,g) V1001.169 -3 211 -3 -2Tm171 (n,g) V1002.321 - 74 - 98Np238 (n,f) V1002.609 54 43 54 35Sr84 (n,g-M) V1001.346 - 34 - 33D. Rochman (O.Cabellos), JEF/DOC-1693 (2015)Fig.4 50Ti(n,g) cross-section

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© 2016 Organisation for Economic Co-operation and Development3.2 Criticality benchmarks3.2.1 Selection of pertinent experiments Methodology for selecting a list of benchmarks for Nuclear Data Validation Start with clean bare configurations, proceed with thermal solutions Include well-tested reflected systems (simple configurations with few materials) More complex assemblies and broad scope testing …. “Expert Judgment” Methodology for Nuclear Criticality and Safety Similarities with the criticality facility …. Expert Judgment3.2.2 The use of Figure of Merit (FoM) Χ2/DoF ….

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© 2016 Organisation for Economic Co-operation and Development3.2.1 Selection of pertinent experiments239Pu, thermal NRG NEAICSBEPCommon Name ENDFB7.1 JEFF-3.3T2 JEFF-3.3T3 JEFF-3.3T1 % Sensitivities C/E C/E C/E C/E U235 U238 U234 Pu239 Pu240 Pu241 SUM N_MATPU-SOL-THERM-001.4 1.005 1.002 0.999 - 0.0 0.0 0.0 68.1 0.1 0.0 71.4 5PU-SOL-THERM-004.1 1.004 0.999 0.996 - 0.0 0.0 0.0 76.7 0.0 0.0 87.3 4PU-SOL-THERM-012.10 1.005 1.000 0.998 - - - - - - - - -PU-SOL-THERM-012.13 1.009 1.004 1.003 - - - - - - - - -PU-SOL-THERM-018.6 1.006 1.004 1.004 - 0.0 0.0 0.0 71.2 5.5 8.8 92.2 6PU-SOL-THERM-034.4 1.003 1.001 0.999 - 0.0 0.0 0.0 76.4 0.1 0.0 88.8 5PU-SOL-THERM-034.15 0.997 1.007 1.003 - 0.0 0.0 0.0 70.6 0.6 0.0 76.9 5PU-SOL-THERM-001.1,.3,.6 1.004 1.002 0.999 - 0.0 0.0 0.0 72.4 0.0 0.0 76.9 4MIX-COMP-THERM-002.30to35 1.000 1.000 1.000 - - - - - - - - -PU-SOL-THERM-023.1 1.004 1.003 1.001 - 0.0 0.0 0.0 73.7 0.3 0.2 76.7 6Methodology for selecting a list of benchmarks that can be used to test specific sets of correlations: Assessment of Experts: ¨The need for Expert Judgement¨ Sensitivities tools? h? ????????=∑?=190238( ∑?=? ,? ,??? , ???? , …❑?? ,???? ×?? ,???? )∑?=1238( ∑?=? ,? ,??? , ???? , …❑?? ,???? ×?? ,???? ) Sensitivities: NMAT: Materials with sens. > 1%

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© 2016 Organisation for Economic Co-operation and Development3.2.1 List of “main” Benchmarks” - A.Trkov (IAEA)CIELO Data Validation and Benchmarking Activities at the IAEA, by A.Trkov, CSEWG-Nov2016Presenting 2-sigma outliers only There could be dependence on less-well known materials The assigned uncertainties of some benchmarks are unreasonably small

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© 2016 Organisation for Economic Co-operation and Development ” ENDF/B-VIII-beta Data Testing at ORNL” by M. Williams, CSEWG Nov 20163.2.1 Expert Judgement: ORNL (289 cases)LEU-COMP-THERM LEU-SOL-THERM MIX-COMP-THERM1-8 LCT 1-001 - 1-008 1-3 LST 2-001 - 2-003 1-4 MCT 1-001 - 1-0049-13 LCT 2-001 - 2-005 4-12 LST 3-001- 3-009 5-7 MCT 2-015, 2-025, 2-03514-43 LCT 10-001 - 10-030 13-19 LST 4-001 - 4-007 8-10 MCT 2-045, 2-055, 2-06544-72 LCT 17-001 - 17-029 11-21 MCT 4-001 - 4-01173-79 LCT 42-001 -42-00744-46 LCT 50-001 - 50-01847-61 LCT 78-001 - 78-01562-72 LCT 80-001 - 80-011HEU-THERM PU-SOL-THERM1-10 HST 1-001 - 1-010 1-6 PST 1-001 - 1-00611-14 HST 13-001 - 13-004 7-13 PST 2-001 - 2-00715-17 HST 14-001 - 14-003 14-21 PST 3-001 - 3-00818-20 HST 16-001 - 16-003 22-34 PST 4-001 - 4-01321-38 HST 28-001 -28-018 35-43 PST 5-001 -5-00939-45 HST 29-001 - 29-007 44-46 PST 6-001 - 6-00346-52 HST 30-001 - 30-007 47-54 PST 7-001 - 7-00855-66 PST 11-001 - 11-01267-81 PST 20-001 - 20-015 THERMAL spectrum

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© 2016 Organisation for Economic Co-operation and Development3.2.1 Expert Judgement: ORNL (289 cases)HEU-MET-FAST PU-MET-FAST IEU-MET-FAST1 HMF 15-001 1 PMF 1-001 1 IMF -0012-3 HMF 16-001 - 16-002 2 PMF 2-001 2 IMF 3-0014 HMF 17-001 3 PMF 5-001 3 IMF 3-0155 HMF 18-001 4 PMF 6-001 4 IMF 4-0016 HMF 18-015 5 PMF 8-001 5 IMF 4-0157 HMF 19-001 6 PMF 10-001 6 IMF 5-0018 HMF 19-015 7 PMF 18-001 7 IMF 5-0159 HMF 20-001 8 PMF 22-001 8 IMF 6-00110 HMF 20-015 9 PMF 23-001 9 IMF 7-00111 HMF 21-001 10 PMF 24-001 10 IMF 8-00112 HMF 21-015 11 IMF 9-00113-17 HMF 25-001 - 25-00518 HMF 30-00119-21 HMF 38-001 - 38-00222 HMF 40-00123 HMF 65-001 ” ENDF/B-VIII-beta Data Testing at ORNL” by M. Williams, CSEWG Nov 2016 FAST spectrum

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© 2016 Organisation for Economic Co-operation and Development3.2.1 Expert Judgement: Skip Kahler (LANL)FAST HST (42) PST (158) LCTHMF, HMI, PMF, PMI & LCT with iron/steel PMFs with various reflectorsHMF 1 (Godiva) HST1 PST1 LCT1 HMF13 LANLHMF28 (Flattop-25) HST9 PST2 LCT2 HMF21 Rocky FaltsPMF1(Jezebel ) HST10 PST3 LCT5 HMF24 IPPEPMF6(Flattop-Pu) HST11 PST4 LCT7 HMF84.7, 84.19 & 85.3 VNIITFIMF7(Big-10) HST12 PST5 LCT8 HMF87 VNIIEFIMF1(Jemima) HST13 PST6 LCT10 HMF88.1&2HMF7 HST32 PST7 LCT17 HMI1HST42 PST9 PMF25HST43 PST10 PMF26HST50 PST11 PMF28PST12 PMF32PST18 PMI2PST22 LCT1PST28 LCT2PST32 LCT10PST34 LCT17PST38 LCT42 ” Testing ENDF/B-VIII.0β Data Files with ICSBEP Benchmarks” by S.Kahler, CSEWG Nov 2016

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© 2016 Organisation for Economic Co-operation and DevelopmentInstitution Library Number casesCEA/CAD JEFF-3.3T1 228IAEA ENDF/B-VII.1 435JEFF-3.3T1 435IRSN JEFF-3.2 19JEFF-3.3T1 19KAERI ENDF/B-VII.1 119JEFF-3.2 119JEFF-3.3T1 119JEFF-3.3T2 119JENDL-4.0u 119LANL ENDF/B-VII.1 1104NEA ENDF/B-VII.1 123JEFF-3.2 123JEFF-3.3T1 123JEFF-3.3T2 123JEFF-3.3T2+ 123JEFF-3.3T2-Skip_INP 119JENDL-4.0 123NRG ENDF/B-VII.1 2445JEFF-3.3T2 2439JEFF-3.3T2+ 2439JENDL-4.0 2445PSI JEFF-3.2 149JEFF-3.3T1 339Total 13948 DICE tool: “Load Personal-keff” DICE tool: “keff trends plots”New options in DICE 2016….sort by C/E, sensitivities, EALF, RRs, …

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© 2016 Organisation for Economic Co-operation and Development3.2.2 The use of Figure of Merit (FoM)Different possibilities for defining Figures of Merit (FoM) exist. These metrics can give reliable indications of the nuclear data performance Average C/E Average difference, r.m.s. Delta-k − magnitude of the average difference between C and E− smaller values better fit to benchamrk Residuals: (kcalc-kexp)/Dkexp Chi-squared, Χ2/DoF − accounts for the uncertainty in the experimental value− sensitive to cases with unrealistically small uncertainties− If x<1 then , on average calculations math benchmarks to within one exp. std. PDFs, CDFs, … % of results within experimental std. dev … other ?

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© 2016 Organisation for Economic Co-operation and DevelopmentProviding compiled results of benchmarkingTable 2. Evaluation of general performance for extended validation suites. Values are “reduced” Chi-squared, number of cases in brackets NRG NEA ENDF/B-VII.1 JEFF-3.3.T2 JEFF-3.3T2+ ENDF/B-VII.1 JEFF-3.3.T2 JEFF-3.3T2+PU 5.8(508)5.7(508)5.5(508)4.2(29)2.8(29)2.4(29)HEU 8.5(890)11.7(894)8.2(894)6.1(42)2.2(42)3.5(42)IEU 1.8(127)1.4(127)1.8(127)5.0(12)2.7(12)2.1(12)LEU 4.3(560)4.0(560)4.3(560)0.9(13)1.8(13)3.7(13)U233 5.3(108)5.2(108)5.6(108)1.7(18)1.7(18)1.9(18)MIX 6.2(252)7.0(252)6.6(252)0.7(8)0.9(8)1.0(8)Total 6.0(2445)6.4(2439)5.6(2439)3.7(123)2.0(123)2.9(123)

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© 2016 Organisation for Economic Co-operation and Development3.3 Shielding and fusion application SINBAD database (e.g. ASPIS/IRON88 - Fe evaluation) Reanalysis of the HCPB and HCLL mockup experiments Cu-Benchmark experiment (FNG/Cu) Methodologies (extensions to the MCNP code) MCSEN (to perform sensitivity analysis), MCUNED (to handle transport of deuterons )A Trkov, EFFDOC-1272 (2015), I. Kodeli, EFFDOC-1295 (2016) K. Takise, O. Cabellos, JEFDOC-1852 (2017)A. Klix, EFFDOC-1294 (2016) M. Angelone, EFFDOC-1281 (2015),… EFFDOC-1326 (2017)A. Klix, EFFDOC-1280 (2015)K. Kondo, EFFDOC-1230 (2014) – R.L. Perel (Israel)I. Kodeli, EFFDOC-1276 (2015) – P. Sauvan (UNED/Spain)

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© 2016 Organisation for Economic Co-operation and DevelopmentGeometry Type-I61 cm diameter vesselType-II40 cm diameter vesselType-III60 cm diameter vesselType –IV28 cm diameter vessel Cu Al Si Nb LiF As Mn Co Mo Cr Zr Se Teflon Ti W Neutron source spectra CASE 1 (Table 4.2) LiF, Mn , Cu, Mo, WCASE 2 (Table 4.3) Teflon, Si, CoCASE 3 (Table 4.4) AlCASE 4 (Table 4.5) Ti, As, Se, ZrCASE 5 (Table 4.6) Cr, NbIII.3 OKTAVIAN TOF Benchmarks(15 cases)Neutron leakage fromOKTAVIAN pulsed sphereEx) 61 cm sphere: Type IF. Maekawa et al., “Collection of Experimental Data for Fusion Neutronics Benchmark”, JAERI, 1994.

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© 2016 Organisation for Economic Co-operation and DevelopmentENDF/B-VIIIb4 FENDL-3.1b JEFF-3.3T2 JEFF-3.3T3 ENDF/B-VIIIb4 FENDL-3.1b JEFF-3.3T2 JEFF-3.3T3Oktavian Zr-40cm Oktavian W-40cm10 MeV < E < 16 MeV 0.97 0.94 0.93 0.94 0.87 0.87 0.88 0.885 MeV < E < 10 MeV 0.96 1.03 1.12 1.05 0.81 0.81 0.80 0.801 MeV < E < 5 MeV 1.19 1.09 1.13 1.10 0.94 0.94 0.87 0.870.5 MeV < E < 1 MeV 1.07 1.06 1.06 1.03 0.81 0.81 0.74 0.740.1 MeV < E < 0.5 MeV 1.23 1.44 1.37 1.38 1.07 1.06 1.13 1.13Table. <C>/<E> values W, T2/T3 lower values below 1 MeV Zr, JEFF/3.3T3 better agreement

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© 2016 Organisation for Economic Co-operation and Development3.4 Burnup BenchmarksFig.17 Comparison of 239Pu cross-sections, fission and capture, JEFF-3.3T2 vs JEFF-3.1.2W. Haeck, JEFF/DOC-1750 (2016)Fig.15 Differences in keff (in pcm) to JEFF-3.1.2 calculation as a function of burnupL.Fiorito, JEFF/DOC-1758 (2016)500 pcm4% pcm This effect is mainly due to the new evaluation of 239Pu 1group integrated 239Pu(n,g) JEFF-3.3T1 is ~1.5% higher than JEFF-3.1.2Fig. 16 Fuell assembly decay heat, Ringhals 2&3 measurements

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© 2016 Organisation for Economic Co-operation and Development3.4 Burnup Benchmark: BUC-PhaseVII“The main objective of this benchmark, is to study the ability of relevant computer codes and associated nuclear data to predict spent fuel isotopic compositions and corresponding keff values, in a cask configuration over the time duration relevant to spent nuclear fuel disposal, up to 1 000 000 years.”Criticality calculationThe criticality model for keff calculations is a representative cask loaded with 21 PWR-UO2 17×17 fuel assemblies. Providing keff values for fresh fuel and isotopic compositions from the decay calculations (30 post-irradiation time steps, out to 1 000 000 years) for two cases involving:o First set (ACT) of 11 actinideso Second set (PFs) involving 14 actinides and 16 fission products

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© 2016 Organisation for Economic Co-operation and DevelopmentFigure. Cask model (side view)Figure. Cask model (top view)PWR UO2 discharge fuel compositions for decay calculations• 4.5-wt% 235U initial enrichment• 50 GWd/MTU burnupReference: John C. Wagner and Georgeta Radulescu, Specification for Phase VII Benchmark UO2 Fuel: Study of spent fuel compositions for long-term disposal, NEA Expert Group on Burn-up Credit, November, 2008

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© 2016 Organisation for Economic Co-operation and Development3.5 Reactor benchmarks and new designs Validation of effective kinetics paramaters (beff and L) based on IRPhE experimentsP. Leconte, JEF/DOC-1722 (2015)P. Tamagno, JEF/DOC-1752 (2016) Experimental reactors

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© 2016 Organisation for Economic Co-operation and Development3.5 Reactor benchmarks and new designsASTRID prototype (600 MWe)Interm. Na circuitDriver core MOXMYRRHA concept (50-100 MWe)Cooled by lead-bismuth lDriver core MOX Start-up core UO2 fuelMOX JEFF-3.2JEFF-3.3T1 Diff.keff 0.99829 1.0018+351 pcmTotal fission probability0.340 0.344 +1.0%Total capture probability0.658 0.654 -0.6%MOX JEFF-3.2 JEFF-3.3T1 Diff.keff 1.00479 1.00737 +258 pcmTotal fission probability0.343 0.346 +1.0%Total capture probability 0.664 0.660 -0.5%UO2 JEFF-3.2 JEFF-3.3T1 Diff.keff 1.01003 1.00001 -1002 pcmTotal fission probability0.408 0.404 -1.0%Total capture probability0.596 0.600 +0.7%P. Romojaro, JEFF/DOC-1756(2016)

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© 2016 Organisation for Economic Co-operation and Development3.6 Covariance verificationICSBEPCase LabelJEFF-3.3T1ENDF/B-VII.1JENDL-4.0Exp. Unc.PCI1-001 2036 547 656 1100HMF1-001 (Godiva)1479 630 882 100IMF3-001 2041 1278 729 170HST032-001119 231 230 260HMI6-001 1600 1996 644 80PMF1-001(Jezebel)304 780 542 129Table 3. Few examples of uncert. (values in pcm)J. Dyrda, JEFF/DOC-1759 (2016)JEFF-3.3T1ENDF/B-VII.1JENDL-4.0 NDaST: Uncertainty Propagation Analysis and comparison with Exp. Uncertainties

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© 2016 Organisation for Economic Co-operation and Development4 Conclusion Review of NEA Tools JANIS, DICE and NDaST The main goals of JEFF- B&V WG are presented Exchange ideas on best practices and procedures for benchmarking Inter-comparisons among different methodologies and validation suites, both problem-dependent and multi-purpose Institutions: NEA, PSI, SCK, CEA, IRSN, JSI, CCFE, KIT, UKAEA, CIEMAT,… The centralization of these tasks relies on the NEA Data Bank Processing, verification, testing and benchmarking tasks (NDEC) NEA Tools: JANIS, DICE, NDaST, …

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© 2016 Organisation for Economic Co-operation and DevelopmentReferences1. M. Chadwick, NDS, 118, (1-25) 20142. JEFF Co-ordination Group, JEF/DOC-1730 (2015)3. O. Cabellos, JEF/DOC-1729 (2015)4. F. Michel-Sendis, JEF/DOC-1625 (2015)5. I. Hill, SG40-15, Ian HILL (2016)6. S. Marck, NDS 113(12), 2935–3005, (2012)7. O. Cabellos, JEF/DOC-1756 (2016)8. M. Fleming, JEF/DOC-1723 (2015)9. R. Ichou, JEF/DOC-1753 (2016)10. D.H. Kim, JEF/DOC-1755 (2016)11. P. Tamagno, JEF/DOC-1752 (2016)12. M. Pecchia, JEF/DOC-1760 (2016)13. D. Rochman, JEF/DOC-1754 (2016)14. S.van der Marck, private communication15. A. Trkov, private communication16. S. Kaheler, private communication17. I. Kodeli, JEF/DOC-1725 (2015)18. A Trkov, EFFDOC-1272 (2015)19. I. Kodeli, EFFDOC-1295 (2016) 20. A. Klix, EFFDOC-1294 (2016) 21. M. Angelone, EFFDOC-1281 (2015)22. A. Klix, EFFDOC-1280 (2015)23. K. Kondo, EFFDOC-1230 (2014)24. I. Kodeli, EFFDOC-1276 (2015)25. A. Stankovskiy, JEF/DOC-1728 (2015)26. K. Ivanov et al., NEA/NSC/DOC(2012) I.27. L. Fiorito, JEF/DOC-1758 (2016)28. W. Haeck, JEF/DOC-1750 (2016)29. M. Fleming, EFFDOC-1293 (2016)30. P. Leconte, JEF/DOC-1722 (2015)31. F. Álvarez, JEF/DOC-1761 (2016)32. J. Dyrda, JEF/DOC-1727 (2015)33. J. Dyrda, JEF/DOC-1759 (2016) 34. E. Nunnenmann, EFFDOC-1275 (2015)35. E. Nunnenmann, EFFDOC-1290 (2016)36. L. Fiorito, JEF/DOC-1726 (2015)…http://www.oecd-nea.org/dbdata/jeff/jeffdoc.htmlhttp://www.oecd-nea.org/dbdata/jeff/effdoc.html

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© 2016 Organisation for Economic Co-operation and Development1) Use DICE to see results of Direct PerturbationLoad keff data, view in “Trend Plots” and compare different results from two different calculations2) Use NDaST to see the effect of switching from JEFF-3.1.1 to ENDF/B-VII.1 Comparison with the “Direct Perturbation” method.The natC(n,g) cross section in ENDF/B-VII.1 and JEFF-3.1.1 and its impact on results of criticality calculations(see JEFDOC-1456)Application to LEU-COMP-THERM-060 RBMK reactor criticality benchmarkExercise – 1.

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© 2016 Organisation for Economic Co-operation and DevelopmentJANIS-DICE-NDAST working in “Local Shared” databases.\\DVD-2016\\ .................................... Folder with DICE data.\\DVD-2016\\DICE2016.\\DVD-2016\\DICE2016\\databases\\H2\\dice.h2.db ... DICE “Local shared” database.\\DVD-2016\\DICE2016\\databases\\H2\\dice.h2.db.0 .. Original DICE “Local” database.\\DVD-2016\\DICE2016\\Java-command-line .......... Folder with shell scripts to run JANIS, DICE and NDaST.\\DVD-2016\\DiceData.\\DVD-2016\\DiceData\\Sensitivity_binary ......... Sensitivity profiles to be used in a “Local Shared” mode

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© 2016 Organisation for Economic Co-operation and Development- Run DICE in “Local shared” mode .\\DVD-2016\\DICE2016\\Java-command-line\\run_dice_in_command_line.bat- Load own keff data (Available only with “Local Shared” database, need to copy DICE to a writeable area) .\\Exercise-1\\LCT60_NRG.txt- View in “Trend Plots”o Compare JEFF-3.1.1 and ENDF/B-VII.1 results for LCT-601. Trend Plots and Personal Keff

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© 2016 Organisation for Economic Co-operation and DevelopmentLEU-COMP-THERM-060 001 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 0.99987 0.00010LEU-COMP-THERM-060 001 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00466 0.00009LEU-COMP-THERM-060 002 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 0.99865 0.00011LEU-COMP-THERM-060 002 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00784 0.00011LEU-COMP-THERM-060 003 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00067 0.00011LEU-COMP-THERM-060 003 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00556 0.00010LEU-COMP-THERM-060 004 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00058 0.00011LEU-COMP-THERM-060 004 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00969 0.00011LEU-COMP-THERM-060 005 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00215 0.00011LEU-COMP-THERM-060 005 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00713 0.00011LEU-COMP-THERM-060 006 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 0.98997 0.00011LEU-COMP-THERM-060 006 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 0.99893 0.00011LEU-COMP-THERM-060 007 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00345 0.00010LEU-COMP-THERM-060 007 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00909 0.00010LEU-COMP-THERM-060 008 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00420 0.00011LEU-COMP-THERM-060 008 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.01500 0.00011LEU-COMP-THERM-060 009 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00454 0.00010LEU-COMP-THERM-060 009 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00992 0.00010LEU-COMP-THERM-060 010 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00059 0.00010LEU-COMP-THERM-060 010 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.01056 0.00010LEU-COMP-THERM-060 011 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00113 0.00010LEU-COMP-THERM-060 011 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00656 0.00010LEU-COMP-THERM-060 012 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00175 0.00010LEU-COMP-THERM-060 012 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00568 0.00010LEU-COMP-THERM-060 013 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00109 0.00010LEU-COMP-THERM-060 013 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00586 0.00010LEU-COMP-THERM-060 014 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 0.99884 0.00011LEU-COMP-THERM-060 014 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00804 0.00011LEU-COMP-THERM-060 015 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00104 0.00011LEU-COMP-THERM-060 015 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00434 0.00010LEU-COMP-THERM-060 016 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 0.99618 0.00011LEU-COMP-THERM-060 016 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00405 0.00011LEU-COMP-THERM-060 017 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00190 0.00009LEU-COMP-THERM-060 017 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00734 0.00010LEU-COMP-THERM-060 018 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 0.99931 0.00011LEU-COMP-THERM-060 018 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00929 0.00011LEU-COMP-THERM-060 019 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00233 0.00010LEU-COMP-THERM-060 019 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00702 0.00010LEU-COMP-THERM-060 020 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00395 0.00011LEU-COMP-THERM-060 020 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.01367 0.00011LEU-COMP-THERM-060 021 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00175 0.00010LEU-COMP-THERM-060 021 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00642 0.00010LEU-COMP-THERM-060 022 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00383 0.00010LEU-COMP-THERM-060 022 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.01288 0.00011LEU-COMP-THERM-060 023 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00311 0.00010LEU-COMP-THERM-060 023 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00744 0.00010LEU-COMP-THERM-060 024 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00241 0.00011LEU-COMP-THERM-060 024 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.01134 0.00010LEU-COMP-THERM-060 025 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00304 0.00010LEU-COMP-THERM-060 025 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00808 0.00010LEU-COMP-THERM-060 026 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00038 0.00010LEU-COMP-THERM-060 026 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00965 0.00010LEU-COMP-THERM-060 027 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00449 0.00010LEU-COMP-THERM-060 027 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.00809 0.00009LEU-COMP-THERM-060 028 Detailed Model MCNP6.1.1 T-ENDF/B-VII.1 1.00237 0.00010LEU-COMP-THERM-060 028 Detailed Model MCNP6.1.1 T-JEFF-3.1.1 1.01055 0.00011JEFF-3.1.1 and ENDF/B-VII.1 results for LCT-60 Benchmarks(calculations using MCNP6.1.1)

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© 2016 Organisation for Economic Co-operation and Development2. NDaST results: Change in Cnat(n,g) using JANIS ratio- Run NDaST using the DICE data in “Local shared” mode .\\DVD-2016\\DICE2016\\Java-command-line\\run_ndast_in_command_line.batPanel 1: Sensitive Benchmark Search Search for LCT-060 cases

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© 2016 Organisation for Economic Co-operation and Development2. NDaST results: Change in Cnat(n,g) using JANIS ratioPanel 2: Isotope-Reaction-Energy Perturbations Auto-computed by dividing two evaluated files (via JANIS) – “Calculate ratios”Example: ENDF/B-VII.1 ÷ JEFF-3.1.2

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© 2016 Organisation for Economic Co-operation and DevelopmentUNITS:0.01 Dkeff/Keff = 1% Dkeff/Keff = 1000 pcmDkeff/KeffDkeff/keff -> change Cnat(n,g): ENDF/B-VII.1 vs JEFF-3.1.1 Panel 3. Launch Perturbation Calculation

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© 2016 Organisation for Economic Co-operation and DevelopmentC/E Keff values JEFF-3.1.1In red, Keff Perturbated values due to the change in Cnat(n,g) ENDF/B-VII.1 versus JEFF-3.1.1In “BLEU” experimental uncertaintyKeff C/EDkeff/keff -> change Cnat(n,g): ENDF/B-VII.1 vs JEFF-3.1.1 Visualization&Results: Select “Benchmark calculations”

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© 2016 Organisation for Economic Co-operation and Development1) Use JANIS to create a new Baseo U235 and Pu239 JEFF-33T4 files (HENDF+BOXER)2) Use DICE to see keff values of a Validation Suiteo NEA calculations3) Use NDaST to calculate the UncertaintiesVisualization C/E + Benchmark uncertainty + ND uncertaintyVisualization ICSBEP Mosteller’s Suite keff values(see JEFDOC-1843)Uncertainty Propagation Analysis and Comparison(see JEFDOC-1850)Exercise – 2.

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© 2016 Organisation for Economic Co-operation and Development- Run JANIS .\\DVD-2016\\DICE2016\\Java-command-line\\run_janis_in_command_line.bat- Use “Import Wizard” tool:o Data library: JEFF-3.3T3o New Base: TRIESTEo U235 and Pu239 files are in:.\\Exercise-2\\JANIS\\HENDF.\\Exercise-2\\JANIS\\BOXER1. Create a new Base named “TRIESTE” using JEFF-3.3T3

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© 2016 Organisation for Economic Co-operation and DevelopmentJANIS-DICE-NDAST working in “Local Shared” databases.\\DVD-2016\\ .................................... Folder with DICE data.\\DVD-2016\\DICE2016.\\DVD-2016\\DICE2016\\databases\\H2\\dice.h2.db ... DICE “Local shared” database.\\DVD-2016\\DICE2016\\databases\\H2\\dice.h2.db.0 .. Original DICE “Local” database.\\DVD-2016\\DICE2016\\Java-command-line .......... Folder with shell scripts to run JANIS, DICE and NDaST.\\DVD-2016\\DiceData.\\DVD-2016\\DiceData\\Sensitivity_binary ......... Sensitivity profiles to be used in a “Local Shared” mode

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© 2016 Organisation for Economic Co-operation and Development- Run DICE in “Local shared” mode .\\DVD-2016\\DICE2016\\Java-command-line\\run_dice_in_command_line.bat- Load own keff data (Available only with “Local Shared” database, need to copy DICE to a writeable area) .\\Exercise-2\\keff_JEFF33T3_MCNP611.txt- View in “Trend Plots”o New MCNP6.1.1 – JEFF-3.3T32. Personal Keff data: “JEFF-3.3T3”

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© 2016 Organisation for Economic Co-operation and DevelopmentHEU-COMP-INTER-003-007 1.00272 0.00037 MCNP6.1 NEA-JEFF-3.3T3HEU-MET-FAST-001-001 Shell Model 1.00023 0.00028 MCNP6.1 NEA-JEFF-3.3T3HEU-MET-FAST-003-001 0.99578 0.00029 MCNP6.1 NEA-JEFF-3.3T3HEU-MET-FAST-003-002 0.99476 0.0003 MCNP6.1 NEA-JEFF-3.3T3HEU-MET-FAST-003-003 1.00016 0.00028 MCNP6.1 NEA-JEFF-3.3T3HEU-MET-FAST-003-004 0.99862 0.00028 MCNP6.1 NEA-JEFF-3.3T3HEU-MET-FAST-003-005 1.00325 0.0003 MCNP6.1 NEA-JEFF-3.3T3……IEU-MET-FAST-001-001 Idealized Model 1.00053 0.00028 MCNP6.1 NEA-JEFF-3.3T3IEU-MET-FAST-001-002 Idealized Model 1.00024 0.00029 MCNP6.1 NEA-JEFF-3.3T3IEU-MET-FAST-001-003 Idealized Model 0.99974 0.00028 MCNP6.1 NEA-JEFF-3.3T3IEU-MET-FAST-001-004 Idealized Model 1.00097 0.0003 MCNP6.1 NEA-JEFF-3.3T3IEU-MET-FAST-002-001 0.99695 0.00026 MCNP6.1 NEA-JEFF-3.3T3….LEU-COMP-THERM-008-001 1.00089 0.00029 MCNP6.1 NEA-JEFF-3.3T3LEU-COMP-THERM-008-002 1.00142 0.00028 MCNP6.1 NEA-JEFF-3.3T3LEU-COMP-THERM-008-005 1.00092 0.00029 MCNP6.1 NEA-JEFF-3.3T3LEU-COMP-THERM-008-007 1.00018 0.0003 MCNP6.1 NEA-JEFF-3.3T3LEU-COMP-THERM-008-008 1.0001 0.00029 MCNP6.1 NEA-JEFF-3.3T3LEU-COMP-THERM-008-011 1.00131 0.0003 MCNP6.1 NEA-JEFF-3.3T3LEU-SOL-THERM-002-001 LEU-SOL-THERM-002-002 0.99307 0.00028 MCNP6.1 NEA-JEFF-3.3T3LEU-SOL-THERM-007-001 0.99189 0.00032 MCNP6.1 NEA-JEFF-3.3T3LEU-SOL-THERM-007-002 0.99473 0.0003 MCNP6.1 NEA-JEFF-3.3T3LEU-SOL-THERM-007-003 0.99329 0.00029 MCNP6.1 NEA-JEFF-3.3T3LEU-SOL-THERM-007-004 0.99581 0.00028 MCNP6.1 NEA-JEFF-3.3T3LEU-SOL-THERM-007-005 0.99495 0.00025 MCNP6.1 NEA-JEFF-3.3T3MIX-COMP-THERM-002-001 Detailed Model 1.00007 0.00034 MCNP6.1 NEA-JEFF-3.3T3MIX-COMP-THERM-002-002 Detailed Model 1.0025 0.00034 MCNP6.1 NEA-JEFF-3.3T3MIX-COMP-THERM-002-003 Detailed Model 1.00031 0.00031 MCNP6.1 NEA-JEFF-3.3T3MIX-COMP-THERM-002-004 Detailed Model 1.00513 0.00033 MCNP6.1 NEA-JEFF-3.3T3MIX-COMP-THERM-002-005 Detailed Model 1.00096 0.00031 MCNP6.1 NEA-JEFF-3.3T3MIX-COMP-THERM-002-006 Detailed Model 1.00293 0.0003 MCNP6.1 NEA-JEFF-3.3T3MIX-MET-FAST-001-001 0.99864 0.00027 MCNP6.1 NEA-JEFF-3.3T3MIX-MET-FAST-003-001 1.00034 0.00028 MCNP6.1 NEA-JEFF-3.3T3….PU-MET-FAST-005-001 1.00172 0.00029 MCNP6.1 NEA-JEFF-3.3T3PU-MET-FAST-006-001 1.00385 0.00031 MCNP6.1 NEA-JEFF-3.3T3PU-MET-FAST-008-001 0.99667 0.00027 MCNP6.1 NEA-JEFF-3.3T3PU-MET-FAST-009-001 0.99896 0.00029 MCNP6.1 NEA-JEFF-3.3T3PU-MET-FAST-010-001 1.00015 0.00028 MCNP6.1 NEA-JEFF-3.3T3…U233-MET-FAST-001-001 1.00022 0.00025 MCNP6.1 NEA-JEFF-3.3T3U233-MET-FAST-002-001 0.99867 0.00026 MCNP6.1 NEA-JEFF-3.3T3U233-MET-FAST-002-002 1.0001 0.00025 MCNP6.1 NEA-JEFF-3.3T3U233-MET-FAST-003-001 0.99888 0.00027 MCNP6.1 NEA-JEFF-3.3T3U233-MET-FAST-003-002 0.99933 0.00027 MCNP6.1 NEA-JEFF-3.3T3U233-MET-FAST-004-001 0.99869 0.00027 MCNP6.1 NEA-JEFF-3.3T3U233-MET-FAST-004-002 0.99695 0.00029 MCNP6.1 NEA-JEFF-3.3T3U233-MET-FAST-005-001 0.99649 0.00029 MCNP6.1 NEA-JEFF-3.3T3U233-MET-FAST-005-002 0.99511 0.0003 MCNP6.1 NEA-JEFF-3.3T3…JEFF-3.3.T3 NEA suiteBenchmarks- 123 cases(calculations using MCNP6.1.1)

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© 2016 Organisation for Economic Co-operation and Development3. NDaST: Use NDaST to calculate ND Uncertainties - Run NDaST using the DICE data in “Local shared” mode .\\DVD-2016\\DICE2016\\Java-command-line\\run_ndast_in_command_line.batPanel 1: File/Open…. NDaST file(e.g. “Mosteller-PU.ndast”) File/Open …“Mosteller-PU.ndast”

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© 2016 Organisation for Economic Co-operation and Development3. NDaST: Use NDaST to calculate ND UncertaintiesPanel 3: Search Covariance Data: “ JEFF-3.3T3 ”Panel 2: Perturbations- To define a “Null perturbation” for downloaded DICE data- Select only “BOXER” format- Use only partial cross-sectionso Delete “MTs” TOTAL

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© 2016 Organisation for Economic Co-operation and DevelopmentPanel 4. Covariance Calculation: “Sandwich formula”Keff C/EIn “BLEU” experimental uncertaintyIn red, Keff JEFF-3.3T3 valuesIn “green” nuclear data uncertainty

Transkript

Compilation Computations Files Perturbation

Anahtar Kelimeler