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

doi:10.7538/yzk.2018.youxian.0749

Abstract

Abstract:

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 of k_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.

Key words: thorium molten salt reactor, Th-U fuel cycle, CENDL-TMSR-V1 nuclear data library, benchmark test

摘要：

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。

关键词: 钍基熔盐实验堆, 钍铀燃料循环, CENDL-TMSR-V1核数据库, 基准检验

WANG Xiaohe;HU Jifeng;CHEN Jingen;CAI Xiangzhou;HAN Jianlong. Benchmark Test of CENDL-TMSR-V1 Nuclear Data Library for Thorium-uranium Fuel Cycle[J]. Atomic Energy Science and Technology, 2019, 53(8): 1466-1474.

王小鹤;胡继峰;陈金根;蔡翔舟;韩建龙. 钍铀燃料循环专用核数据库CENDL-TMSR-V1的基准检验[J]. 原子能科学技术, 2019, 53(8): 1466-1474.

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