摘要
核电厂建造期间,反应堆压力容器密封盖用于隔断换料水池和反应堆,密封边界长且依靠自重密封。文中进行了压力容器密封盖泄漏分析和结构强度分析,结果表明,压力容器密封盖设计满足使用要求;结合分析和现场使用情况,提出了进一步的改进建议。
At the stage of nuclear power plant construction,reactor pressure vessel seal cover is used to isolate refueling pool and reactor with its long sealing boundary and self-weight sealing method.This paper analyzes the leakage and strength of the seal cover firstly,the results show that design meets requirements.Improvement suggestion is proposed according to service condition and analysis results finally.
作者
瓮松峰
张弦
熊思勇
殷琪
湛卉
WENG Songfeng;ZHANG Xian;XIONG Siyong;YIN Qi;ZHAN Hui(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu 610213,China)
出处
《机械工程师》
2020年第7期78-80,共3页
Mechanical Engineer
关键词
反应堆压力容器
密封盖
泄漏分析
强度校核
reactor pressure vessel
seal cover
leakage analysis
strength checking