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McCARD Criticality Benchmark Analyses with Various Evaluated Nuclear Data Libraries

Author

Listed:
  • 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)

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.

Suggested Citation

  • Ho Jin Park & Mohammad Alosaimi & Seong-Ah Yang & Heejeong Jeong & Sung Hoon Choi, 2022. "McCARD Criticality Benchmark Analyses with Various Evaluated Nuclear Data Libraries," Energies, MDPI, vol. 15(18), pages 1-17, September.
    • Handle: RePEc:gam:jeners:v:15:y:2022:i:18:p:6852-:d:919116
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