摘要
反应堆压力容器快中子注量计算是反应堆工程设计和国家核安全监管部门关注的一项重要内容,在计算中不可避免地采用一些模型简化方法,这些简化方法将对计算结果产生一定的影响。利用MC方法计算程序MCNP对反应堆压力容器快中子注量计算过程中的模型简化方法开展研究,评估这些简化方法的利弊,为压力容器快中子注量计算提供合理建议,保障计算的严谨性。
The calculation of reactor pressure vessel fast neutron flux is one of the important aspects for reactor designing and safety reviewing. There will be some simplifications, which may lead to a certain impact on the results, in the calculation unavoidably. The simplification methods used in the calculation of reactor pressure vessel fast neutron flux are studied; the advantages and disadvantages are estimated. Some suggestions which would make the calculation more scientific are provided.
出处
《核电子学与探测技术》
CAS
北大核心
2015年第12期1201-1204,共4页
Nuclear Electronics & Detection Technology
基金
大型先进压水堆及高温气冷堆核电站国家科技重大专项(2013ZX06002001)资助
关键词
压力容器
快中子注量
MC方法
reactor pressure vessel
fast neutron flux
Monte Carlo method
