摘要
压力容器的使用期限:直接决定了反应堆的寿命,而快中子注量是影响其使用期限的重要参数之一,是核安全审评中关注的一项重要内容。作为核安全监管部门,对大型先进压水堆CAP1400的压力容器快中子注量进行审核计算,能够促进审评的独立性、科学性和有效性,为CAP1400的安全审评提供良好技术支持。本文利用蒙特卡罗方法分析程序对CAP1400反应堆压力容器快中子注量进行独立审核计算,并将计算结果与反应堆设计方利用离散纵标法所得结果进行对比。结果表明,CAP1400反应堆压力容器快中子注量审核计算结果与设计值的相对偏差在10%以内,并且快中子注量值满足标准审评大纲的相关要求。
The lifetime of the pressure vessel,which depends on the value of fast neutron flux,restricts the lifetime of the reactor directly.The fast neutron flux is a focus in nuclear safety review.As a nuclear safety regulator,the independent verification calculation of the fast neutron flux in CAP1400 reactor pressure vessel makes the safety review more independent,scientific and effective,and provides a good technical support.This paper illustrates the independent verification calculation of the fast neutron flux in CAP1400 reactor pressure vessel u-sing the Monte Carlo method.And the results are compared with those of the design,which are calculated by the discrete ordinate method.The standard deviation between the verifying and designing calculations is lower than 10%,and the results meet the requirements of the standard review plan.
作者
刘巧凤
韩静茹
LIU Qiao-feng;HAN Jing-ru(Nuclear and Radiation Safety Center,Beijing 100082,China)
出处
《中国核电》
2018年第4期462-465,共4页
China Nuclear Power
基金
国家科技重大专项资助项目(2017ZX06004002-001)
关键词
辐射屏蔽
独立审核计算
压力容器快中子注量
radiation shielding
independent verification calculation
fast neutron flux in pressure vessel
