TENDL-2012 processing, verification and validation steps

Transcription

1 TENDL-2012 processing, verification and validation steps Jean-Christophe SUBLET 1*, Arjan KONING 2 and Dimitri ROCHMAN 2 1 UK Atomic Energy Authority, Culham Science Centre, Abingdon OX14 3DB, United Kingdom 2 Nuclear Research and Consultancy Group, NL-1755 ZG, Petten, The Netherlands CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority

2 Incident-neutron data: 2434 isotopes Incident-proton data: 2429 isotopes Incident-deuteron data: 2428 isotopes Incident-triton data: 2348 isotopes Incident-He3 data: 2429 isotopes Incident-alpha data: 2429 isotopes Incident-gamma data: 2430 isotopes TENDL-2012 (January 2013) All evaluations to 200 MeV, with covariance on n- incident and 30 Mev high energy format cutoff. Extending the nuclear data needed for fusion, fast, high energy applications while keeping the abilities for fission modelling. 2

3 TENDL s philosophy From model parameters to code result quantities Allow physical parameters to impact the basic nuclear data and not an engineered localized adjustment, unable to account for compensation effects. Cater for all applications: fission, fusion, astrophysics, With variance-covariance data based on experimental data and nuclear models, allowing design optimization of nuclear technology. Account for the processing (non unique) steps. Include, account for V&V Verification and Validation processes. Feedback of extensive validation and benchmark activities are automatically and rapidly, within a year not 10, taken into account. 3

4 Processing steps Not one not two.but three processing codes are used in sequence and in parallel to produce, shape, check, and compare the nuclear data NJOY, PREPRO and CALENDF Robustness, redundancy, portability, availability, accessibility, repeatability, legacy and maturity All processing steps cannot be handle by only one or even two of those quite unique processing codes!!! 4

5 Processing steps: transport Monte Carlo pointwise neutron, multi-temperature libraries with probability tables in the URR using NJOY and CALENDF-2010 For TRIPOLI-4.9 (with CALENDF-2010 PT s) For MCNP For MCNPX For SERPENT-1 or -2 From n-tendl-2012, neutron induced data 5

6 Processing steps: burnup, transmutation Multi-particles groupwise, multi-temperature libraries with NJOY , PREPRO-2012, probability tables in the RR & URR with CALENDF-2010 For the inventory code FISPACT-II From α, γ, p, d, n-tendl-2012 FISPACT-II parses directly the TENDL s covariance information Transport and activation applications libraries now stem from unique, truly general purpose files 6

7 NJOY reconr broadr unresr thermr heatr gaspr purr Groupr acer ACE file cross-check PREPRO-2012 linear recent sigma1 sixpack activate merger dictin groupie ENDF file Processing steps cross-check CALENDF-2010 calendf regroutp lecritp. PT file Single script for all TENDL files 7

8 8 Neutron n-tendl-2012

9 9 Neutron n-tendl-2012

10 Gamma data γ-tendl Cross section (barns) Incident Energy (MeV)

11 EASY-II TENDL s libraries 1 GeV n-tendl-2012, multi temperatures, 709 groups library with covariance and PT s; 2434 targets γ-tendl-2012, 162 groups library, 2430 targets p-tendl-2012, 162 groups library, 2429 targets d-tendl-2012, 162 groups library, 2428 targets α-tendl-2012, 162 groups library, 2429 targets new decay data library-2012, 3873 isotopes new hazards, clearance and transport indices libraries, 3873 isotopes JEFF-3.1, UKFY4.1 fission yields 11

12 Differential Verification and Validation V&V C/E with the latest EXFOR, C/C with EAF s, ENDF s files SACS: Statistical Analysis of Cross Section; Kopecky & Forrest legacy systematics. Integral Criticality TRIPOLI-4.9 ICSBEP suite (130 cases) MCNP6 SvdM NRG ICSBEP suite (1900 cases) Transport, shielding MCNP6 SvdM NRG Sinbad and LLNL suites Activation-transmutation, decay heat EASY-II validation suite (500 reactions rates, thousands of integral E, time dependent, fusion orientated) MACS and RI: Maxwellian-averaged cross sections and astrophysical reaction rates, resonance integrals 12

13 Automated EAF / TENDL / EXFOR plot Cross section (mb) Cr(n,2n) 51 Cr Araminowicz 1973 Bormann 1968 Deak 1974 Ercan 1991 Fessler 1998 Ghorai 1987 Ikeda 1988 Iwasaki 1997 Liskien 1989 Lychagin 1988 Mannhart 2007 Maslov 1972 Molla 1983 Molla 1997 Qaim 1972 Ribansky 1985 Sailer 1977 Uno 1996 Wagner 1989 Wenusch 1962 ZhouFengQun 2005 EAF 2010 TENDL Energy (MeV) 13 Some ~1700 EXFOR graphs!!

14 Automated EAF / TENDL / EXFOR plot 56 Fe(n,p) 56 Mn 160 EAF 2010 TENDL Cross section (mb) Energy (MeV) 14

15 Automated EAF / TENDL / EXFOR plot 87 Rb(n,2n) 86m Rb Cross section (mb) Energy (MeV) 15 Important partial cross section

16 Automated EAF / TENDL / EXFOR plot 93 Nb(n, ) 90m Y Cross section (mb) Energy (MeV) 16 Important partial cross section

17 Automated EAF / TENDL / EXFOR plot 89 Y(n,2n) 88 Y Cross section (mb) Energy (MeV) Important total cross section 17

18 Proton data p-tendl-2012 nat Fe(p,x) 54 Mn 100 Stuck 1983 Michel 1980 Michel 1979 Cross section (mb) Schoen 1979 Barchuk 1987 Zhao Wenrong 1993 Williams 1967 Brodzinski 1971 Al Abyad 2009 Sudar 1994 Ditroi 2004 Rayudu 1964 Michel `1997 Daum 1997 Daum 1997 eval Zhao Wenrong 1993 Shoen 1979 Jenkins 1970 TENDL TENDL 2011 Proton energy (MeV) 18

19 TRIPOLI-4.9 ICSBEP s fast range Code Tripoli-4.6 Tripoli-4.6 Tripoli-4.7 Tripoli-4.9 Library JEFF BRC-2009 ENDF/B.VII.1 TENDL-2012 Experiment Calc. Calc. Δ Calc. Δ Calc. Δ Keff Unc. Kcalc S.D. Kcalc (C-C) Kcalc (C-C) Kcalc "(C%C) ICSBEP IMF-007 Name Cyl. U Metal (10% 235U), thick 238U Reflector Big Ten deta simp Δ (C-E) t.z.h Δ (C-E) IMF-012 Cyl. U Metal (16% 235U), Al and Steel, Reflected by Depleted-U ZPR(16%) c Δ (C-E) IMF-10 Cyl U Metal (9% 235U), thick Depleted U Reflector ZPR-U9 c Δ (C-E) IMF-002 Nat. U Reflected Assembly of Enriched U Plates c Δ (C-E) IMF-001 Fast Range Bare Cyl. Conf. of Enriched and Natural U Jemima c c c Average Δ (C-E) TENDL-2012 perform well in the fast range ( Δk > Δ exp. shaded)

20 TRIPOLI-4.9 ICSBEP s fast range Code Tripoli-4.6 Tripoli-4.6 Tripoli-4.7 Tripoli-4.9 Library JEFF BRC-2009 ENDF/B.VII.1 TENDL-2012 Experiment Calc. Calc. Δ Calc. Δ Calc. Δ Keff Unc. Kcalc S.D. Kcalc (C-C) Kcalc (C-C) Kcalc (C-C) ICSBEP Name Fast Range HMF U Sphere Reflected by Normal U using Flattop Flattop Δ (C-E) HMF-001 Bare, Highly Enriched U Sphere Godiva c c Average Δ (C-E) PMF-001 Bare Sphere of Pu-239 Metal Jezebel c Δ (C-E) PMF-002 Bare Sphere of Pu-239 Metal Jez. 240 c Δ (C-E) &46 20 Godiva!! the culprit is U 234 ; lesson, one cannot pick only one or two actinides. BRC all U s methodology, also based on TALYS, is only safe way forward How can you expect to properly simulate (not fit) the thermal range If you do not get it right in the fast (fission birth) range??

21 TRIPOLI-4.9 ICSBEP s Thermal range Code Tripoli-4.6 Tripoli-4.6 Tripoli-4.7 Tripoli-4.9 Library JEFF BRC-2009 ENDF/B-VII.1 TENDL-2012 Experiment Calc. Calc. Δ Calc. Δ Calc. Δ Keff Unc. Kcalc S.D. Kcalc Δ (C-C) Δ (C-C) Kcalc Δ"(C%C) ICSBEP Name Thermal range U LCT-006 Low Enriched UO2 Fuel Rods with # Water-to-Fuel Volume Ratios c c c c c c c c Average Δ (C-E) %27 LCT-007 Water Reflected Wt.% Enriched UO2 Fuel Rod Arrays Valduc c c c c c c Average Δ (C-E) The LWR references, TENDL-2012 is as good as..

22 TRIPOLI-4.9 ICSBEP s Thermal range Code Tripoli-4.6 Tripoli-4.6 Tripoli-4.7 Tripoli-4.9 Library JEFF BRC-2009 ENDF/B-VII.1 TENDL-2012 Experiment Calc. Calc. Δ Calc. Δ Calc. Δ Keff Unc. Kcalc S.D. Kcalc Δ (C-C) Δ (C-C) Kcalc Δ (C-C) ICSBEP Name Thermal range U LCT-039 Incomplete Arrays of Water Reflected Wt.% Enriched UO2 Fuel Rods Valduc c c c Average Δ (C-E) Hector k Experiments in Intermediate Neutron Spectra for 235U Hiss Δ (C-E) ICSBEP MCT-004 Name Mox 3.01 wt% PuO2-UO2 fuel rods, Thermal range Pu 2.4 w/f ratio c w/f ratio c w/f ratio c w/f ratio c Average Δ (C-E) Mox interesting trend, are the solution (HST) reliable?? 22

23 JAEA FNS Assembly; decay heat 14 MeV neutrons are generated by a 2 ma deuteron beam impinging on a stationary tritium bearing titanium target; Fusion Neutron Source FNS Neutron spectra, neutron fluence monitored by 27 Al(n,α)Na 24 Two experimental campaigns: 1996 and 2000; 74 materials 23

24 JAEA FNS Assembly: decay heat WHOLE ENERGY ABSORPTION SPECTROMETER PMT Hamamatsu R (K-free type) Dark Box 120φ x 100mm Large BGO Scintillator X-Ray Shield Copper (5mm) +Acryl (5mm) PMT Lead Shield Detector Support Irradiated Sample (25 x 25 x 0.01 mm) Detection Efficiency ~ 100 % for both beta- and gamma-rays 24

25 Decay power: FNS JAERI Inconel 600 FNS-00 5 Min. Irradiation - Inc600 Half life (years) min day FNS Experiment EAF-2010 TENDL-2011 TENDL-2012 Heat Output [µw/g] Co 53 V 52 V Product Pathways T½ Path % E/C 52 V 52 Cr (n, p ) 52 V 3.7m Cr (n, d ) 52 V Mn (n, a ) 52 V Mn 56 Fe (n, p ) 56 Mn 2.5h V 62m Co 56 Mn 60m Co Ni Time after irradiation [minutes] 25

26 Decay power: FNS JAERI Yttrium FNS-00 5 Min. Irradiation - Y 2 O 3 Half life (years) min day m Y FNS Experiment EAF-2010 TENDL-2011 TENDL-2012 Heat Output [µw/g] N 86m Rb Product Pathways T ½ Path % E/C 16 N 16 O (n, p ) 16 N 7.1s m Y 89 Y (n, n') 89m Y 15.6s m Rb 89 Y (n, a ) 86m Rb 1.0m Y 89 Y (n, 2n) 88 Y 106.6d Y Time after irradiation [minutes] 26

27 2434 targets (H 1 to Ds 281 ) Cross section, 90 reaction types Decay data: 3873 nuclides; 24 types Stables and isomeric states; g, m, n, o,.. x3 x 1.7 α, γ, n, p, d- TENDl-2012 (2011) Covariance ENDF/B, JENDL, JEFF 1E+01 Validation: SACS Decay-2012 UKFY-2012 Cross section (b) 1.5E E E E-01 Y-89(n,2n)Y-88 Systm PAT79 RI 99 KGU00 LAS75 KYU79 MOH84 ANL87 BRC81 LAS75 KOS81 FEI89 FEI89 SAV98 BRC02 RI 99 LAS75 AUB76 JAE93 LAS77 AEP89 Max cross section (b) 1E+00 1E-01 1E-02 1E Asymmetry (s) Indices 1.50 C/E C/E = C/E = C/E = C/E = C/E = C/E = C/E = C/E = C/E = Neutron Spectrum C/E = C/E = C/E = C/E = C/E = C/E = C/E = sneg_2 fng_f82h.asc cf252_flux_1 cf252_flux_1 cf252_flux_1 fzk_ss316 fng_vanad.asc rez_df fns_7hour cf252_flux_1 cf252_flux_1 fzk_ss316 fng_eurofer.asc sneg_1 fzk_2 fzk_ E E E E E E E E+07 Energy (ev) Final V&V, C/E integral and differential with uncertainty 27

28 Conclusions With TENDL-2012(2011), the NRG library s have entered the secluded world of criticality benchmarking TENDL-2012 uniquely contain covariance information TENDL-2012 provides for all applications: transport, burnup, inventory, transmutation, dosimetry, astrophysics, TENDL-2012 has fully benefited from TENDL-2008, 2009, 2010, 2011, EAF s V&V and the T6 technological construction framework n-tendl-2012 evaluated nuclear data libraries already outwit the regional majors: ENDF, JENDL, JEFF,.. However, low z isotopes still will need to come from R-matrix theory and actinides from carefully nurture TALYS model TENDL-2012: reliable, V&V libraries for all applications 28

29 Acknowledgement We would like to gratefully acknowledge the mature advices, understanding, willingness and contributions of Dermott E. Cullen, Robert E. MacFarlane and Pierre Ribon without whom we would not have been able to reach our goal. 29