摘要
介绍了在秦山300MW核电机组全范围模拟机组上进行的主冷却剂系统汽相破口模拟实验及其结果。通过实验结果与设计分析计算结果的比较,找出异同,为此类事故处理提供指导。同时,进一步探索了秦山核电厂发生此类事故时的电厂响应;处理此类事故的较好方法以及事故处理过程中的关键点。
he paper introduces the vapour phase rupture simulating test of reactor coolant system on the full scope simulator for Qinshan 300MW nuclear power unit.Through comparing test results with design values of the unit,this paper try to find the difference among them and try to give reactor operation information on handling the accident.This paper research the response if the accident occurred in Qinshan nuclear power unit,discusses the better method and key point to handle the accident.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
1998年第3期198-202,229,共6页
Nuclear Power Engineering
关键词
反应堆
冷却剂系统
汽相破口
模拟实验
核电站
inshan 300MW nuclear power unit Reactor coolant system Vapour rupture Simulating test