Benchmark Calculations in Support for FENDL-3 Generation Mohamed Sawan Tim Bohm Fusion Technology Institute The University of Wisconsin-Madison 2 nd RCM.

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Benchmark Calculations in Support for FENDL-3 Generation Mohamed Sawan Tim Bohm Fusion Technology Institute The University of Wisconsin-Madison 2 nd RCM on FENDL March 2010 IAEA, Vienna

Outline Application of ENDF/B-VII.0 to FNG integral experiments Proposed material addition to FENDL-3 Benchmark analysis for initial FENDL-3 startup library (release 2) Problems with processed data Benchmark analysis for corrected FENDL-3 startup library M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 2

M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 3 Data Source for FENDL-2.1 Total 71 elements/isotopes

M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 4  Majority (40) of materials in FENDL-2.1 taken from ENDF/B-VI.8  We investigated the effect of the recently released ENDF/B-VII.0 data (December 2006) on results for the FNG ITER relevant integral experiments  Examined tungsten, bulk shielding, streaming and HCPB breeder mock-ups  Compared calculated to experimental results (C/E) for 3 cases ⁃ FENDL-2.1 ⁃ All FENDL-2.1 data replaced by ENDF/B-VII.0 ⁃ FENDL-2.1 with data for the 40 materials only replaced by ENDF/B-VII.0 ENDF/B-VII.0 Applied to ITER Relevant FNG Experiments

FNG Experiments Analyzed M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 5 Tungsten Bulk shielding Streaming HCPB breeder

Tungsten experiment activation foils M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 6 ReactionE threshold (MeV)FENDL-2.1ENDF/B-VIIPartial ENDF/B-VII Mn-55(n,  )Mn / / /1.771 Au-197(n,  )Au / / /1.093 Ni-58(n,p)Co / / /1.075 In-115(n,n')In-115m* / / /0.862 Al-27(n,  )Na / / /1.047 Fe-56(n,p)Mn / / /0.930 Ni-58(n,2n)Ni / / /1.049 Zr-90(n,2n)Zr / / /1.057 Nb-93(n,2n)-Nb / / /1.056 Average/Maximum of Calc/Exp

Bulk Shielding experiment activation foils M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 7 ReactionE threshold (MeV)FENDL-2.1ENDF/B-VIIPartial ENDF/B-VII Mn-55(n,  )Mn / / /0.743 Au-197(n,  )Au / / /0.802 Ni-58(n,p)Co / / /0.701 In-115(n,n')In-115m* / / /0.500 Al-27(n,  )Na / / /0.787 Fe-56(n,p)Mn / / /0.786 Ni-58(n,2n)Ni / / /0.876 Zr-90(n,2n)Zr Nb-93(n,2n)-Nb / / /0.776 Average/Maximum of Calc/Exp

Streaming experiment activation foils M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 8 ReactionE threshold (MeV)FENDL-2.1ENDF/B-VIIPartial ENDF/B-VII Ni-58(n,p)Co / / /1.100 Al-27(n,  )Na / / /0.713 Nb-93(n,2n)-Nb / / /0.827 Average/Maximum of Calc/Exp

HCPB Breeder activation foils M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 9 ReactionE threshold (MeV)FENDL-2.1ENDF/B-VIIPartial ENDF/B-VII Au-197(n,  )Au / / /0.853 Ni-58(n,p)Co / / /0.935 Al-27(n,  )Na / / /1.034 Nb-93(n,2n)-Nb / / /0.929 Average/Maximum of Calc/Exp

HCPB Breeder tritium production M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 10 Depth (mm)FENDL-2.1ENDF/B-VIIPartial ENDF/B-VII / / / / / / / / / / / /0.838 Average/Maximum of C/E values at each 12 pellet ENEA group

Finding M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 11 Calculations of foil activation and tritium breeding for ITER relevant FNG integral experiments yield nearly similar results for FENDL-2.1 and ENDF/B-VII.0

M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 12 FENDL-3/SLIB Starter Library A starter library (FENDL-3/SLIB) was generated based on several agreed upon rules of creation –Replace present evaluations with updates –Adopt evaluations from libraries that contain standards (H-1 from ENDF) –Use isotopic evaluations where available The library includes 88 isotopes with updated evaluations from ENDF/B-VII.0, JENDL-HE, JEFF-3.1, and BROND Only evaluation switch between libraries occurred for H-1 and He-3 (JENDL-3.3  ENDF/B-VII.0) that could impact analysis of systems with water-cooling like ITER Sn is the only material with elemental rather than isotopic evaluation FENDL-3/SLIB materials –47 from ENDF/B-VII.0 –35 from JENDL-HE –4 from JEFF-3.1 –2 from BROND-2

M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 13 Proposed Added Materials in FENDL-3 Following the 1 st RCM meeting in December 2008, we reviewed the list of material in the FENDL-2.1 general purpose data library regarding its completeness to satisfy the needs for fusion neutronics analysis We solicited input from the fusion neutronics community for possible addition of materials that are needed and are missing from the FENDL-2.1 library 17 elements were identified for consideration to be added in the new library to enhance its usefulness for the different fusion applications We identified the application needed for each proposed material and gave a priority to help us with decision if we want to limit the number of materials added Availability of evaluations for these elements was determined In addition, 6 isotopes are missing from FENDL-2.1 and need to be considered for inclusion in FENDL-3

17 Elements Proposed for Addition in FENDL-3 M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 14

17 Elements Proposed for Addition in FENDL-3 (continued) M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 15

M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna Elements Proposed for Addition in FENDL-3 (continued) These cover all materials requested by ITER (M. Loughlin) except Cs, U, Th, Np Additional materials needed for IFMIF analysis were provided by U. Fischer

Six Isotopes Missing for Elements in FENDL  Abundances for C-13 and Pb-204 are significant and inclusion in FENDL-3 should be considered  O-18 and V-50 have low abundances and no evaluations and could be ignored in FENDL-3  Although O-17 and W-180 have very low abundances, evaluations exist for them and could be considered for FENDL-3 M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna

M. Sawan 18 ITER Calculational Benchmark  To quantify impact of data changes, we performed MCNP calculations for a 1-D ITER calculational benchmark that was utilized during FENDL development process  Calculations carried out using FENDL-2.1 library, FENDL-2.1 with data for the 40 materials replaced by ENDF/B- VII.0, and the FENDL- 3/SLIB library (release 2 posted 6/24/2009 designated SLIB2)  Results for flux, heating, dpa, and gas production were compared 2nd RCM on FENDL-3, March 2010, IAEA, Vienna

M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 19 Findings of Data Comparison Between ENDF/B-VI.8 and ENDF/B-VII.0  Minor impact on ITER nuclear analysis is expected except for ITER-TBM nuclear analysis due to changes in data for Li-6, Pb-208, and F-19  Effects of changes could be large in other fusion systems Power plants with breeding blankets Inertial fusion systems (e.g., H-3 and Au-197 data are important for ICF target neutronics) 1.M.E. Sawan, “Benchmarking FENDL-2.1 with Impact of ENDF/B-VII.0 Release on Nuclear Heating and Damage,” Proceedings of the 23rd IEEE/NPSS Symposium on Fusion Engineering (SOFE), May 31-June 5, 2009, San Diego, CA, ISBN No , IEEE Cat. No. CFP09SOF-CDR. Also University of Wisconsin Fusion Technology Institute Report, UWFDM-1361 (May 2009) 2.M. Sawan, “Impact of ENDF/B-VII.0 Release on Fusion Evaluated Nuclear Data Library FENDL-2.1,” Fusion Science & Technology, vol. 56, pp (August 2009)

M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 20 Peak Neutron and Gamma Flux Results Using ENDF/B-VII.0 data results in slightly higher flux values. However, the change is <1% with much smaller differences at the front FW zones facing the plasma Using FENDL-3/SLIB2 results in much higher flux values particularly at the magnet that is heavily shielded by water-cooled SS shield and vacuum vessel

M. Sawan 21 Neutron Spectra Using FENDL-3/SLIB2 results in significantly softer neutron energy spectrum at the heavily shielded outboard magnet that yields enhanced gamma generation At OB magnet E>0.1 MeV flux increases by only 3% while the E<0.1 MeV flux increases by 82% 2nd RCM on FENDL-3, March 2010, IAEA, Vienna

M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 22 Peak Nuclear Heating Results While using ENDF/B-VII.0 data results in slightly higher heating values (<1%) using FENDL-3/SLIB2 results in much higher heating values particularly at the magnet Most of increase in outboard magnet heating is due to gamma heating increase (21% increase vs. 5% increase in neutron heating)

M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 23 Peak Magnet Nuclear Parameters While using ENDF/B-VII.0 data results in slightly higher magnet parameters using FENDL-3/SLIB2 results in much higher parameters with the largest increase in magnet heating due to enhanced gamma production

FENDL-3/SLIB2 Calculations for FNG Bulk Shield Experiment M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 24  Small difference compared to FENDL-2.1  Bulk shield mock-up thickness is much smaller than magnet shielding in ITER

M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 25  To further investigate the increase in low energy (E<0.1 MeV) neutron flux observed in the ITER 1-D calculational benchmark with FENDL- 3/SLIB2 we performed simple calculations for slabs with all water, all SS316, and SS316/H 2 O mixture  Compared neutron fluxes in the various slabs calculated with MCNPX using FENDL-2.1 versus FENDL-3/SLIB  Used isotropic 14.1 MeV neutron source 5% increase FENDL-3/SLIB2 in Slabs of H 2 O, SS316 and SS/H 2 O (80/20)

M. Sawan 26 30% increase 750% increase Observed large differences are not related to change in H data but are related to SS data 2nd RCM on FENDL-3, March 2010, IAEA, Vienna

FENDL-3/SLIB2 in Mo Slab M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna % increase Performed calculations for slabs made of each constituent element of SS316 Largest difference obtained in Mo (JENDL-3.3  JENDL-HE) Mo resonances are below 0.1 MeV compared to higher energy resonances for Fe Resonance data might have changed or data processing with NJOY might have an error

Revised FENDL-3 Starter Library M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 28  Independent assessment by Andrej Trkov confirmed the large differences  An anomaly was noticed in plots of neutron emission spectra  The symptoms suggested that it is likely an NJOY processing problem which is very specific for the combination of data representation in the JENDL-HE files  A temporary patch to NJOY was proposed that solves processing problems for all affected materials  New processed ACE files were posted on 2/16/2010  We performed calculations with the corrected FENDL-3 starter library designated FENDL-3/SLIB2a and compared results to FENDL-2.1 and the previous FENDL-3/SLIB2a

M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 29 Peak Neutron and Gamma Flux Results with FENDL-3/SLIB2a Using the corrected FENDL-3 starter library (FENDL-3/SLIB2a) removed the large overestimate at deep penetration locations Neutron and gamma fluxes at VV and magnet that are heavily shielded by water-cooled SS are higher by 1-3% than predicted by FENDL-2.1

M. Sawan 30 Neutron Spectrum at OB Magnet with FENDL-3/SLIB2a Using FENDL-3/SLIB2a corrected the anomaly in low energy spectrum caused by wrong secondary energy spectra Energy spectra from FENDL-3/SLIB2a and FENDL-2.1 are close with differences up to ~10% at E>2 MeV 2nd RCM on FENDL-3, March 2010, IAEA, Vienna

M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 31 Notable change in FENDL-3 is switch for H-1 from JENDL-3.3 to ENDF/B-VII.0 Lower (n,) cross sections at high energy could be reason for higher neutron flux (particularly at high energy) in regions heavily shielded by water-cooled SS H-1 Data in FENDL-3 vs. FENDL-2.1

M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 32 Peak Nuclear Heating Results with FENDL-3/SLIB2a Using the corrected FENDL-3 starter library (FENDL-3/SLIB2a) removed the large overestimate at deep penetration locations Nuclear heating at magnet is higher by ~2% than predicted by FENDL-2.1

M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 33 Peak Magnet Nuclear Parameters with FENDL-3/SLIB2a Nuclear parameters at magnet are higher by ~ % than predicted by FENDL-2.1 Largest differences are in fast neutron fluence and dpa that are determined by high energy flux

FENDL-3/SLIB2a in Slabs of SS/H 2 O (80/20) M. Sawan 34 No large differences observed with corrected library (FENDL-3/SLIB2a) 2nd RCM on FENDL-3, March 2010, IAEA, Vienna

FENDL-3/SLIB2a in Mo Slab No large differences observed with corrected library (FENDL-3/SLIB2a) M. Sawan 35 2nd RCM on FENDL-3, March 2010, IAEA, Vienna

M. Sawan 2nd RCM on FENDL-3, March 2010, IAEA, Vienna 36 Conclusions  Replacing the ENDF/B-VI.8 data in FENDL-2.1 by ENDF/B-VII.0 while keeping data from other evaluations unchanged resulted in minor change (<1%) in nuclear parameters for ITER relevant calculations  However, larger changes in calculated ICF target neutronics parameters and tritium breeding were observed in previous analysis  Calculations of foil activation and tritium breeding for ITER relevant integral experiments yield nearly similar results for FENDL-2.1 and ENDF/B-VII.0  Using FENDL-3/SLIB2 instead of FENDL-2.1 resulted in large increase in nuclear parameters behind the thick water-cooled shield. This was identified as processing error and was corrected in FENDL-3/SLIB2a  Using FENDL-3/SLIB2a instead of FENDL-2.1 in ITER relevant calculations gives 2-4% higher nuclear parameters in regions that are heavily shielded with water-cooled SS (vacuum vessel, magnets)