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- W2937264246 abstract "Abstract The McCARD criticality, depletion, and S/U analyses with the newly published evaluated nuclear data file (ENDF) library ENDF/B-VIII.0 are conducted and their results are compared with those using the previous version of ENDF library, ENDF/B-VII.1. First of all, to verify and validate the newly generated ENDF/B-VIII.0 continuous energy cross section library in the ACE format, 60 cases from International Criticality Safety Benchmark Problems (ICSBEP) and VENUS-1 criticality benchmark analyses are performed using the McCARD code. Overall, the prediction performance of criticality is retained except for the high enriched uranium (HEU) fast and plutonium-based (PU) thermal benchmarks. The large difference in keff for the HEU fast and PU thermal benchmarks comes from the increase of the 238U capture cross sections in the fast energy region and the decrease of 239Pu fission cross section in the thermal energy region, respectively. In the results for the VERA depletion benchmarks, the large differences at the end of the burnup can be attributed to the difference of the one-group 235U absorption cross section. It leads to the increases of the difference in kinf between ENDF/B-VIII.0 and ENDF/B-VII.1 as the burnup proceeds. In the ENDF/B-VIII.0 evaluated nuclear data library, there have been considerable changes in the covariance data. The changes have a strong correlation with the decreases in the total uncertainty of multiplication factor for Godiva and the TMI-1 pin problem." @default.
- W2937264246 created "2019-04-25" @default.
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- W2937264246 date "2019-09-01" @default.
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- W2937264246 title "Comparison of ENDF/B-VIII.0 and ENDF/B-VII.1 in criticality, depletion benchmark, and uncertainty analyses by McCARD" @default.
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- W2937264246 doi "https://doi.org/10.1016/j.anucene.2019.04.012" @default.
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