TENDL-2011 processing and criticality benchmarking

Transcription

1 JEF/DOC-1438 TENDL-2011 processing and criticality benchmarking Jean-Christophe C Sublet UK Atomic Energy Authority Culham Science Centre, Abingdon, OX14 3DB United Kingdom CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority

2 December TENDL-2011 release contents Incident-neutron data: 2424 isotopes Incident-proton data: 2429 isotopes Incident-deuteron data: 2419 isotopes Incident-triton data: 2431 isotopes Incident-He3 data: 2428 isotopes Incident-alpha data: 2429 isotopes Incident-gamma data: 2428 isotopes All evaluations to 200 MeV with covariance on n-induced

3 Processing steps: transport Monte Carlo pointwise multi-temperatures libraries with probability tables in the URR: For TRIPOLI-4.8 with NJOY and CALENDF-2010 For MCNP with NJOY For MCNPX with NJOY For SERPENT-1 or -2 with NJOY From TENDL-2011s20, neutron induced data

4 Processing steps: burnup, transmutation EAF s format style libraries are been phased out, replaced by ENDF s style libraries, however the physics input streams remain: JUKO legacy s This has been made possible because of: November 2010 CSWEG ENDF-6 format extension NJOY-99 extensions: mf8, reconr basic, acer, gaspr PREPRO-2010 extensions: sixpack, complot, TENDL-2011 new format framework: unequivocal, clear format 20, 30 or 60 MeV then to 200 MeV. The development of the FISPACT-II inventory code

5 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 All processing steps cannot be handle by only one or even two of those quite unique processing codes!!!

6 Processing steps NJOY moder reconr broadr unresr heatr gaspr purr groupr acer Ø PREPRO linear recent sigma1 sixpack activate merger dictin groupie CALENDF-2010 calendf regroutp lecritp. PT file ENDF file

7 Differences in formalism interpretation Cubic interpolation for CALENDF but PREPRO and CALENDF interpretations are similar Differences between 1.0 and 2.0 Kev and only on the fission channel!!

8 Processing steps are not unique!! 293.6K 0K!! Competition (3 51) opens at 77 ev, in the RR. NJOY-99 default broadening stops, not PREPRO or CALENDF max energy for broadening and thinning = E max energy for broadening and thinning = E+03

9 Processing steps are not unique!! CALENDF s resonances in the URR

10 Emitted spectra energy distribution edges Smoothing: in PREPRO first, then NJOY, MCNP!! LLNL UCRL-TR

11 EASY-II(12) libraries 1 GeV n-tendl-2011, multi temperatures, 709 groups library with covariance and PT s; 2429 targets γ-tendl-2011, 162 groups library, 2428 targets p-tendl-2011, 162 groups library, 2429 targets d-tendl-2011, 162 groups library, 2419 targets α-tendl-2011, 162 groups library, 2429targets dec-2012, 3873 isotopes hazards, clearance and transport indices libraries

12 TENDL-2011 pendf, 200 MeV

13 TENDL-2011 pendf, 200 MeV APPM OF He 4 = 1.13E+03 APPM OF He 3 = 1.30E-02 APPM OF H 3 = 1.43E-18 APPM OF H 2 = 2.07E+01 APPM OF H 1 = 1.18E+03 NJOY generated MT s displayed by PREPRO

14 TENDL-2011 pendf, 200 MeV Kerma rates Dpa rate NJOY generated MT s displayed by PREPRO

15 TENDL-2011 pendf from mf3*mf6 Unique to PREPRO-2010+

16 TENDL-2011 gendf, 200 MeV From PREPRO or NJOY

17 TENDL-2011 gamma pendf All of the changes made for TENDL-2011 will be included in PREPRO-2012

18 Libraries, ICSBEP benchmarks, Transport code JEFF neutron induced library (=JEFF in those cases) BRC-2009 = JEFF-3.2β (isotopes replaced in JEFF with E h = 30 Mev; Am241, Pu238, Pu239, Pu240, U235, U236, U237, U238, U239 ENDF/B-VII.1 neutron induced library (Dec. 2011) TENDL-2011 neutron induced library (Dec. 2011), with H1, H2 and thermal compounds data from JEFF A 100 s selected benchmarks from the International Handbook of Evaluated Criticality Safety Benchmark Experiments With the Monte Carlo code TRIPOLI-4, 293.6K pointwise data and CALENDF probability tables in the URR for every isotopes that contains one

19 TRIPOLI-4 ICSBEP s Fast range Code Tripoli-4.6 Tripoli-4.6 Tripoli-4.7 Tripoli-4.8 Library JEFF BRC-2009 ENDF/B.VII.1 TENDL-2011 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 IMF-007 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 Bare Cyl. Conf. of Enriched and Natural U Jemima c c c Average Δ (C-E) TENDL-2011 perform well in the fast range

20 TRIPOLI-4 ICSBEP s Fast range Code Tripoli-4.6 Tripoli-4.6 Tripoli-4.7 Tripoli-4.8 Library JEFF BRC-2009 ENDF/B.VII.1 TENDL-2011 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) PNFS Pu s (239 and 240 JEF/DOC-1359) and fast U235 data Only BRC-2009 compare well to ENDF/B-VII.1 How can you expect to properly model (not fit) the thermal range If you do not get it right in the fast (but still fission) range??

21 TRIPOLI-4 ICSBEP s Thermal range Code Tripoli-4.6 Tripoli-4.6 Tripoli-4.7 Tripoli-4.8 Library JEFF BRC-2009 ENDF/B-VII.1 TENDL-2011 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) LCT-007 Water Reflected Wt.% Enriched UO2 Fuel Rod Arrays Valduc c c Average Δ (C-E) LCT-039 Incomplete Arrays of Water Reflected Wt.% Enriched UO2 Fuel Rods Valduc c c c Average Δ (C-E) TENDL-2011 O16 & U238!! known correction

22 TRIPOLI-4 ICSBEP s Thermal range Code Tripoli-4.6 Tripoli-4.6 Tripoli-4.7 Tripoli-4.8 Library JEFF BRC-2009 ENDF/B-VII.1 TENDL-2011 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-027 Water Moderated and Lead Reflected 4.75% Enriched UO2 Rod Arrays Pb refl. c Δ (C-E) LCT-10 Water-Mod. U(4.31)O2 Fuel Rods Reflected by Two Lead, Uranium, or Steel Walls Pb refl. c Δ (C-E) Pb refl. c Δ (C-E) ICSBEP Name Thermal range Pu MCT-004 Mox 3.01 wt% PuO2-UO2 fuel rods, 2.4 w/f ratio c w/f ratio c w/f ratio c w/f ratio c Average Δ (C-E) Lead impact and Mox interesting trend

23 Conclusions With TENDL-2011, the NRG library s have entered the secluded world of criticality benchmarking TENDL-2011 uniquely contain covariance information TENDL-2011 provides for all applications: transport, burnup, inventory, transmutation, dosimetry, astrophysics, TENDL-2011 has fully benefited from TENDL-2008, 2009, 2010, EAF s V&V and the T6 technological construction framework n-tendl-2011 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 è TENDL-2012

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