反应堆压力容器快中子注量计算基准验证  

Benchmark Verification on Calculation of Reactor Pressure Vessel Fast Neutron Flux

作　　者：刘巧凤 韩向臻 马帅 彭京洋 赵传奇 吴永乐 LIU Qiao-feng;HAN Xiang-zhen;MA Shuai;PENG Jing-yang;ZHAO Chuan-qi;WU Yong-le(Nuclear and Radiation Safety Center,Ministry of Ecology and Environment,Beijing 100082,China)

机构地区：[1]生态环境部核与辐射安全中心,北京100082

出　　处：《核电子学与探测技术》2019年第5期592-596,共5页Nuclear Electronics & Detection Technology

基　　金：国家科技重大专项(2017ZX06004002—001)资助。

摘　　要：反应堆压力容器快中子注量计算是反应堆屏蔽设计及核安全审评中的一项重要内容,利用MC法开展该项计算通常采用目前较为公认的建模及计算方法.选取 H.B.ROBINSON-2国际基准题,通过基准验证,证明反应堆压力容器快中子注量的建模及计算方法合理.在此基础上,针对计算过程中的几何简化方法进行敏感性分析,结果表明,对外围组件进行pin-by-pin模拟是必要的.Calculations of reactor pressure vessel fast neutron flux are important contents in reactor radiation shielding design and nuclear safety review.Generally acknowledged method is usually adopted for modeling and calculating with MC method at present.The H.B.ROBINSON-2 benchmark was chosen to do the verification on calculation of reactor pressure vessel fast neutron flux,and the rationality of the modeling and calculating method was proved.Then,the sensitivity analysis was made on geometry simplification method in the computational process.The results showed that it was necessary to simulate the outer assemblies in pin-by-pin pattern in calculations.

关 键 词：快中子注量 基准题 H.B.ROBINSON-2 

分 类 号：TL48[核科学技术—核技术及应用]