摘要
地震情况下核电站非能动堆芯冷却系统(PXS)能否可靠运行对核电站的安全性有着重要影响。本文采用故障树方法分析计算了PXS各部件在峰值地面加速度(PGA)为0.5g、1.5g、2.5g情况下的失效概率以及各部件对系统失效的贡献,并与《AP1000概率安全分析报告》中的抗震裕量分析(SMA)方法的结果进行比较,分析部件的抗震能力。结果表明:本文方法计算的条件失效概率和各部件对系统失效的贡献与SMA方法的结果基本相符。本文方法可为AP1000等非能动核电站的安全分析提供参考。
The reliable operation of passive core cooling system（PXS）has an important effect on safety of nuclear power plant under earthquake.The FT（fault tree）method was used to calculate the failure probability of each subsystem of PXS with peak ground acceleration（PGA）at 0.5 g,1.5 gand 2.5 grespectively and the contribution of components to system failure probability.The calculation results were compared with results of seismic margin analysis（SMA）method in ＂AP1000 Probabilistic Risk Assessment＂and the anti-seismic ability of equipment was analyzed.The results show that the conditional failure probability and the contribution of each component to the system failure are in accordance with the results of the SMA method.The method can provide reference for the safety analysis of AP1000.
作者
庞博
玉宇
汪彬
PANG Bo;YU Yu;WANG Bin(School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China;Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy North China Electric Power University, Beijing 102206, China)
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2018年第5期896-903,共8页
Atomic Energy Science and Technology
基金
国家科技重大专项资助项目(2015ZX06002007)
核反应堆系统设计技术重点实验室项目资助
关键词
非能动堆芯冷却系统
可靠性分析
条件概率
passive core cooling system
reliability analysis
conditional probability
