摘要
压水堆核电厂"半环"运行时丧失余热排出系统的事故后果非常严重。为研究该事故进程,本工作以300 MW级压水堆核电厂为研究对象,对"半环"运行工况下丧失余热排出系统的事故进程进行研究。分析发现,主泵检修和蒸汽发生器人孔打开工况易因丧失冷却剂而使堆芯裸露,堆芯温度迅速升高,并引发熔堆的事故风险。而当一回路系统闭口时,系统压力将升高很快,存在系统超压风险。
In a pressurized water reactor （PWR） nuclear power plant, the risk of loss of residual heat removal system at mid-loop operation is very significant. Thermal-hydraulic behaviors of mid-loop operation with loss of residual heat removal were analyzed. When reactor coolant pump and steam generator are under inspection and maintainance, the core losses coolant and temperature increases, which results in core melton. But when primary system is closed, the pressure of the reactor coolant system increases quickly and the system overpressures.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2009年第5期452-456,共5页
Atomic Energy Science and Technology
基金
国家重点基础研究发展计划资助项目(2009CB724301)
关键词
“半环”运行
丧失余热排出系统
轴封开口
mid-loop operation
loss of residual heat removal system
seal open
