钍铀燃料循环专用核数据库CENDL-TMSR-V1的基准检验

中国科学院上海应用物理研究所委托中国核数据中心研制了钍铀燃料循环专用核数据库CENDL-TMSR-V1，用于钍基熔盐实验堆的临界计算及屏蔽设计。为验证该数据库的可靠性，根据钍基熔盐实验堆的特点，从国际核临界安全手册中挑选了一系列基准实验装置进行基准检验。检验结果表明，绝大部分基准装置的k_eff计算结果与实验数据的相对误差在0.5%以内，证明CENDL-TMSR-V1具有较好的可靠性和适用性，可用于钍基熔盐实验堆的物理设计。

Benchmark Test of CENDL-TMSR-V1 Nuclear Data Library for Thorium-uranium Fuel Cycle

A nuclear data library CENDL-TMSR-V1 for thorium-uranium fuel cycle was developed by China Nuclear Data Center in collaboration with Shanghai Institute of Applied Physics (SINAP), Chinese Academy of Sciences (CAS) for the critical analysis and shielding design of thorium molten salt reactor (TMSR). In order to validate the reliability of CENDL-TMSR-V1, a series of benchmark tests from the international criticality safety benchmark experiment handbook were selected for testing by considering the key characteristics of TMSR. The test results show that the relative error ofk_eff between the calculated value and the experimental one is less than 0.5% for most benchmark experiments, which indicates that CENDL-TMSR-V1 has a high accuracy and reliability, and it is therefore suitable for the physical design of TMSR.