钍铀循环专用核数据库CENDL-TMSR  

The special nuclear data library CENDL-TMSR for thorium-uranium cycle

作　　者：刘萍[1] 陈国长 吴小飞[1] 舒能川[1] 黄小龙[1] 张环宇[1] 葛智刚[1] LIU Ping;CHEN GuoChang;WU XiaoFei;SHU NengChuan;HUANG XiaoLong;ZHANG HuanYu;GE ZhiGang(China Nuclear Data Center,China Institute of Atomic Energy,Beijing 102413,China;National Natural Science Foundation of China,Beijing 100085,China)

机构地区：[1]中国核数据中心,中国原子能科学研究院,北京102413 [2]国家自然科学基金委,北京100085

出　　处：《中国科学：物理学、力学、天文学》2020年第5期73-87,共15页Scientia Sinica Physica,Mechanica & Astronomica

摘　　要：钍基熔盐堆核能系统(TMSR)为第四代先进核能系统,需要更先进、更可靠的物理设计,而核数据的可靠性对于核设计精度有着至关重要的影响.受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循环专用核数据库CENDL-TMSR,包括微观评价核数据库和宏观参数库,以用于钍基熔盐实验堆的临界计算以及屏蔽设计.为验证钍铀循环专用核数据库的可靠性与适用性,对该库进行了临界基准检验与屏蔽基准检验.临界检验结果表明,绝大部分基准装置的keff计算值与实验值的相对误差都在0.5%之内,表明该数据库是可靠的,可用于钍基熔盐实验堆的物理设计.屏蔽计算结果与实验数据基本吻合,整体性能优于其他评价核数据库.Thorium molten salt reactor nuclear energy system(TMSR), which is the fourth generation advanced nuclear energy system, needs more advanced and reliable physical design. The reliability and accuracy of nuclear data has very important impact on the accuracy of nuclear design. According to the requirement of Shanghai Institute of Applied Physics, Chinese Academy of Sciences, China Nuclear Data Center has developed a special nuclear data library CENDLTMSR for thorium-uranium cycle, which includes evaluated nuclear data library and application libraries for criticality calculation and shielding design of thorium molten salt reactor. In order to verify and validate the reliability and applicability of the CENDL-TMSR, the criticality benchmarking and shielding benchmarking are carried out. The criticality testing results show that the relative errors between calculated keffand experimental values for most benchmarks are within 0.5%, which indicates that the CENDL-TMSR can be used for physical design of thorium molten salt reactor. The shielding calculation results are consistent with the experimental ones, and the overall performances are better than other evaluated nuclear data libraries.

关 键 词：钍基熔盐堆 核数据库 钍铀燃料循环 

分 类 号：TL426[核科学技术—核技术及应用] TP311.13[自动化与计算机技术—计算机软件与理论]