摘要
介绍了秦山第二核电厂600 MW压水堆机组的辐照监督计划,对监督、试验、评价方法以及超前因子偏大的原因进行了分析讨论。根据辐照监督数据评价了秦山第二核电厂反应堆压力容器辐照脆化效应。
This paper describes the vessel radiation surveillance program for Qinshan second nuclear power plant 600MWe pressurized water reactor. Surveillance program, test, evaluation method and origins for larger lead factor were discussed in detail. The effect of radiation embrittle for reactor pressure vessel for Qinshan second nuclear power plant was evaluated on the basis of the results of two surveillance capsules.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2008年第6期83-86,共4页
Nuclear Power Engineering
关键词
反应堆
压力容器
辐照脆化
监督
Reactor, Pressure vessel, Radiation embrittle, Surveillance
