地震下非能动堆芯冷却系统可靠性分析  

Seismic Reliability Analysis for Passive Core Cooling System

作　　者：庞博 玉宇[1,2] 汪彬[1,2] 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)

机构地区：[1]华北电力大学核科学与工程学院,北京102206 [2]华北电力大学非能动核能安全技术北京市重点实验室,北京102206

出　　处：《原子能科学技术》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

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.

关 键 词：非能动堆芯冷却系统 可靠性分析 条件概率 

分 类 号：TL364.5[核科学技术—核技术及应用]