摘要
介绍了CANDU堆核电厂的严重事故过程、AECL对CANDU严重事故进行的分析研究和对秦山三期核电厂进行的较为详细的核电厂一级PSA分析。分析结果表明,在对抗严重事故方面CANDU堆有着优良的特性,秦山三期堆芯严重损坏概率满足我国和国际通常的目标限值。
The process of CANDU NPP severe accident is introduced, and then CANDU NPP severe accident and Qinshan Phase Three NPP level one PSA made by AECL are analyzed. The results show that the CANDU NPP is with good capability to withstand severe accident, and that the core damage frequency of Qinshan Phase Three NPP meets the objective limit used in the world and China.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2003年第S2期13-15,69,共4页
Nuclear Power Engineering
关键词
CANDU堆
核电厂
严重事故
CANDU reactor
Nuclear power plant
Severe accident
