严重事故下核电站安全壳内氢气分布及控制分析  

Analysis of Hydrogen Distribution and Control in NPP Containment during Severe Accidents

作　　者：方立凯[1] 陈松[1] 周全福[1] 

机构地区：[1]上海核工程研究设计院堆芯设计室,200233

出　　处：《核动力工程》2006年第z1期18-22,共5页Nuclear Power Engineering

摘　　要：使用安全壳分析程序CONTAIN计算分析了百万千瓦级压水堆核电站严重事故下安全壳内的氢气浓度分布。分别对一回路冷段大破口失水(LB-LOCA)叠加应急堆芯冷却系统(ECCS)失效(不包括非能动的安注箱)事故和全厂断电(SBO)叠加汽轮机驱动的应急给水泵失效事故两个严重事故序列进行了计算。计算结果表明,不同严重事故下,安全壳各隔间对氢气控制系统的要求不同。氢气控制系统的设计必须满足不同事故下的法规要求,提高电站的安全性。CONTAIN code was used to calculate the hydrogen distribution in the containment of 1000 MW NPP during severe accidents in this article.Two sequences of severe accidents were selected in the system shall be designed to meet the requirement of safety review and to improve the safety of 1000 MW NPP.analysis: the first was large break LOCA in cold leg with ECCS(emergency core cooling system) failure;and the second was SBO with failure of emergency feed pump driven by turbine.The results showed that different hydrogen control requirements are needed for different accidents in various compartments.Hydrogen control

关 键 词：氢气浓度分布 严重事故 大破口失水事故 全厂断电 

分 类 号：TL364+.4[核科学技术—核技术及应用]