摘要
对事故后一些物理现象下的堆外中间量程测量通道IRC(Intermediate Range Channel)的响应进行了分析,包括停堆后(N-1)组控制棒组件下落、反应堆水池淹没、堆芯空泡份额或堆芯裸露等。分析发现,事故工况下IRC的响应并不一定反映堆芯次临界度的变化。从状态导向事故运行程序SOP(State Oriented Procedure)堆芯次临界度监测的目的出发,对SOP中堆芯次临界度监测阈值的选取和一回路状态功能监测优先级的确定给出了建议。
the responses of IRC(Intermediate Range Channel) to some physical phenomena in post accident,including the drop down of reactor cluster control assemblies(N-1) after reactor trip,the flooding of reactor pit,reactor core void fraction and reactor core exposed etc,are analyzed.Analysis result shows that the response of IRC does not always reflect the state of subcriticality in reactor core in accident conditions.From the purpose of core subcriticality monitoring in SOP(State Oriented Procedure) point of view,the threshold selection of core subcriticality monitoring and priority determination of primary state function monitoring in SOP are suggested.
出处
《核电子学与探测技术》
CAS
CSCD
北大核心
2014年第6期736-739,共4页
Nuclear Electronics & Detection Technology
关键词
状态导向
次临界
状态功能
阈值
事故运行程序
state oriented
subcriticality
state function
threshold
operating procedure