摘要
介绍了用于模块化沸水堆的先进非能动余热排出系统(RHRS)的设计,比较了两种具有不同回路结构的RHRS方案,并对主换热器置于不同位置时对RHRS排热能力的影响进行了分析。对主蒸汽阀关闭和给水管破裂两类事故的分析表明:设计的非能动余热排出系统能有效地将余热从堆中排出,保证堆芯始终不发生裸露。
This paper studied the passive residual heat removal system(PRHRS) installed in SSBWR- 200. Two schemes with different loop structures are compared, and effect of location of main heat exchanger on the RHRS performance is also studied. Analysis of two accidents, i.e. main steam isolate valve (MISV) closure and feedwater system piping break, proves that RHRS of SSBWR-200 is with the ability to remove the residual heat effectively from RPV to atmosphere.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2003年第S2期9-12,共4页
Nuclear Power Engineering
关键词
小型简化沸水堆
非能动余热排出系统
事故分析
Small simplified BWR(SSBWR)
Passive residual heat removal system(RHRS)
Accident analysis.