基于灵敏度对比分析SCALE 6.1自带库与CENDL-TMSR-V1数据库

为满足钍基熔盐堆物理设计和钍铀燃料循环物理分析对核数据的需求，中国核数据中心研制了一套钍铀燃料循环专用数据库CENDL-TMSR-V1。本文利用SCALE程序，针对熔盐堆开展了SCALE 6.1自带数据库和CENDL-TMSR-V1库对比分析。结果显示，针对1 GWt钍增殖熔盐堆，利用两个数据库的238群数据计算的不同燃耗下k_eff最大差异约1 200 pcm。结合核数据对keff的灵敏度分析显示，其差异主要由石墨的核数据不同引起的。宏观检验结果显示，CENDL-TMSR-V1库中石墨数据更合理。同时，基于CENDL-TMSR-V1 44群协方差数据，计算得到核数据对初始时刻k_eff总不确定度为1.03%，约为SCALE 6.1自带44群协方差数据库计算结果的2倍，其差异主要由²³³U、²³²Th等核素的协方差数据不同导致。

Comparison between SCALE 6.1 Built-in Library and CENDL-TMSR-V1 Library with Sensitivity Analysis

In order to meet the needs of physical design of thorium molten salt reactor (TMSR) and physical analysis of thorium uranium fuel cycle for nuclear data, CENDL-TMSR-V1 library was developed by China Nuclear Data Center. The comparison between SCALE 6.1 built-in library and CENDL-TMSR-V1 library was performed by SCALE. The results show that for 1 GWt thorium molten salt breeder reactor, the maximum difference of keff between the two libraries is about 1 200 pcm within the burnup period. The sensitivity analysis of nuclear data to keff shows that the difference is mainly caused by the difference of graphite nuclear data. The result of the benchmark tests shows that the graphite nuclear data in CENDL-TMSR-V1 is more reasonable. Based on CENDL-TMSR-V1 44 groups covariance data library, the total uncertainty of nuclear data for keff at the beginning of life is 1.03%, which is about twice the calculation result of SCALE 6.1 built-in 44 groups covariance library, and the main difference is caused by the different covariance data of 233U, 232Th, etc.