压水堆核电厂主蒸汽隔离阀阀体端部尺寸超差应力分析研究  

Stress Analysis at Valve End of the Main Steam Isolation Valve for PWR Nuclear Power Plant

作　　者：王岩 张强升 黄炳臣 孟阿军 WANG Yan;ZHANG Qiangsheng;HUANG Bingchen;MENG Ajun(Nuclear and Radiation Safety Center,Beijing 100082,China;Shenzhen China Nuclear Power Design Co.,Ltd.,Shenzhen of Guangdong Prov.518045,China)

机构地区：[1]生态环境部核与辐射安全中心,北京100082 [2]深圳中广核工程设计有限公司,广东深圳518045

出　　处：《核科学与工程》2023年第1期104-110,共7页Nuclear Science and Engineering

摘　　要：本文以国内某压水堆核电机组的主蒸汽隔离阀阀体与超级管道连接段为例,按照RCC-M标准对减薄主蒸汽隔离阀阀体内径至与超级管道内径一致进行研究。同时,借助有限元软件Ansys对阀体减薄后的主蒸汽隔离阀开展应力分析,证明阀门仍然满足RCC-M标准及技术规格书的要求。结合理论分析及有限元模型模拟结果,证明主蒸汽隔离阀阀体端部尺寸超差通过减薄主蒸汽隔离阀阀体内径这一解决措施是可行的。In this paper,taking the main steam isolation valve body and super-pipe connection segment of a PWR nuclear power plant in China as an example,according to the RCC-M standard,the diameter of the reduced main steam isolation valve body is consistent with the inner diameter of the super-pipe.At the same time,with the help of the finite meta-software Ansys,the main steam isolation valve after the valve body is thinned to carry out stress analysis to prove that the valve still meets the requirements of RCC-M standards and specifications.Combined with theoretical analysis and simulation results of the finite factor model,it is proved that the solution of the difference in size of the end of the main steam isolation valve body is feasible by reducing the internal diameter of the main steam isolation valve.

关 键 词：压水堆 主蒸汽隔离阀 应力分析 超级管道 ANSYS 

分 类 号：TL329[核科学技术—核技术及应用]