Evaluation of CENDL-3.2 and CENDL-TMSR-V1 on zero power experimental benchmark of Molten Salt Reactor Experiment

摘要: The 2019 edition of the International Reactor Physics Evaluation Project (IRPhEP) Handbook incorporated the Molten Salt Reactor Experiment (MSRE) benchmark, providing keff (effective multiplication factor) values derived from first criticality experiments and control rod worth calculations for multiple nuclear data libraries including ENDF/B-VII.1. This benchmark constitutes the first comprehensive reference case for molten salt reactor physics, having been extensively utilized to assess the consistency and accuracy of Monte Carlo codes and nuclear data libraries in molten salt reactor modeling. Since 2011, the Thorium Molten Salt Reactor (TMSR) nuclear energy system has been under development at the Shanghai Institute of Applied Physics, Chinese Academy of Sciences to facilitate thorium resource utilization. In support of this initiative, the China Nuclear Data Center developed specialized CENDL-TMSR-V1 libraries tailored for thorium-uranium fuel cycles. Nevertheless, the verification status of Chinese nuclear libraries CENDL-3.2 and CENDL-TMSR-V1 in molten salt reactor applications remains unexplored. In this work, a high-fidelity MSRE model was developed using OpenMC, with comparative analyses conducted across four evaluated nuclear data libraries: ENDF/B-VII.1, ENDF/B-VIII.0, CENDL-3.2, and CENDL-TMSR-V1. A systematic evaluation of neutronic parameters was performed, encompassing reactivity coefficients, control rod differential worth, zero-power flux distribution, and 500-day burn-up calculations. Key findings reveal that: The relative deviations in keff between all libraries and IRPhEP benchmark values remain below 300 pcm (0.3% Δk/k). The maximum relative discrepancy in power distribution predictions between CENDL-series libraries and ENDF/B-VII.1 is <2%. The keff deviations during burn-up calculations are maintained within 0.2%/. This study validates the applicability of CENDL-series libraries for molten salt reactor neutronic simulations.