摘要
通过概率安全分析(PSA)发现,在华龙一号核电机组设计过程中,中压安注泵关闭扬程的降低虽然有利于满足蒸汽发生器传热管破裂(SGTR)事故的验收准则,但造成丧失直流电事故的堆芯损坏频率(CDF)上升。对此针对性地提出了在事故处理规程中增加快速卸压阀用于充-排的优化方案。将该方案应用于华龙一号核电机组,PSA结果表明,丧失直流电事故的CDF由2.4×10-8 (堆·年)-1下降至2.2×10-9(堆·年)-1。因此,本文提出的优化方案有效降低了机组风险。
Through the probability safety analysis(PSA), it is found that in the design process of HPR1000, the reduction of the medium safety injection pump shut off head is beneficial to meet the steam generator tube rupture(SGTR) accident acceptance criteria, but it increases the core damage frequency(CDF) of loss of direct current accident. This paper puts forward the optimization scheme to add the rapid pressure relief valves for feed and bleed in the accident procedure. Applying this scheme to HPR1000, the PSA results show that the CDF of loss of direct current accident decreases from 2.4×10-8(reactor·year)-1 to 2.2×10-9(reactor·year)-1. So the optimization scheme proposed in this paper effectively reduces the risk of HPR1000.
作者
杨健
邓纯锐
马超
Yang Jian;Deng Chunrui;Ma Chao(China Nuclear Power Engineering Co.Ltd.,Beijing,100840,China;Nuclear Power Institute of China,Chengdu,610213,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2019年第6期114-117,共4页
Nuclear Power Engineering