McCARD Criticality Benchmark Analyses with Various Evaluated Nuclear Data Libraries

Ho Jin Park, Mohammad Alosaimi, Seong-Ah Yang, Heejeong Jeong and Sung Hoon Choi ()
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Ho Jin Park: Department of Nuclear Engineering, Kyung Hee University, Yongin 17104, Korea
Mohammad Alosaimi: King Abdullah City for Atomic and Renewable Energy, Riyadh 12244, Saudi Arabia
Seong-Ah Yang: Department of Nuclear Engineering, Kyung Hee University, Yongin 17104, Korea
Heejeong Jeong: Korea Atomic Energy Research Institute, Daejeon 34057, Korea
Sung Hoon Choi: Korea Atomic Energy Research Institute, Daejeon 34057, Korea

Energies, 2022, vol. 15, issue 18, 1-17

Abstract: International Criticality Safety Benchmark Evaluation Project (ICSBEP) criticality analyses were conducted using the McCARD Monte Carlo code for 85 selected benchmark problems with 7 evaluated nuclear data libraries (ENDLs): ENDF/B-VII.1, ENDF/B-VIII.0, JENDL-4.0, JENDL-5.0, JEFF-3.3, TENDL-2021, and CENDL-3.2. Regarding the analyses, it was confirmed that the k eff results are sensitive to the ENDL. It is noted that the new-version ENDLs show better performance in the fast benchmark cases, while on the other hand, there are no significant differences in k eff among the different ENDLs in the thermal benchmark cases. The sensitivity of the k eff results depending on the ENDL may impact nuclear core design parameters such as the shutdown margin, critical boron concentration, and power defects. This study and k eff results will be a good reference in the development of new types of nuclear cores or new design codes.

Keywords: Monte Carlo; McCARD; criticality analysis; ICSBEP; ENDF/B-VIII.0; ENDF/B-VII.1; JENDL-4.0; JENDL-5.0; TENDL-2021; CENDL-3.2; JEFF-3.3 (search for similar items in EconPapers)
JEL-codes: Q Q0 Q4 Q40 Q41 Q42 Q43 Q47 Q48 Q49 (search for similar items in EconPapers)
Date: 2022
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