蒸汽爆炸载荷下压力容器和主管道力学分析  

Mechanical Analysis of Pressure Vessels and Main Pipes under Steam Explosion Loads

作　　者：唐鹏 姚迪 余力 罗娟[1] 周鼎 Tang Peng;Yao Di;Yu Li;Luo Juan;Zhou Ding(Nuclear Power Institute of China,Chengdu,610213,China)

机构地区：[1]中国核动力研究设计院,成都610213

出　　处：《核动力工程》2022年第S01期127-131,共5页Nuclear Power Engineering

摘　　要：针对华龙一号反应堆压力容器(RPV),研究其在假设蒸汽爆炸载荷下RPV和主管的力学响应。通过建立有限元模型并根据瞬态结构分析方法开展数值分析,得到了RPV和主管道的变形、应力和应变结果。计算结果表明:RPV在600、800、1000℃下的失效载荷分别为1/20、1/50和1/100设计载荷;最大等效应力/应变均位于接管附近;主管道大部分区域应力未超过管道屈服应力。本研究可为RPV极端载荷下的结构完整性分析提供技术支持。The mechanical response of HPR1000 reactor pressure vessel(RPV)and its main pipe under the hypothetical steam explosion load is studied.Through the establishment of the finite element model and the numerical analysis according to the transient structure analysis method,the deformation,stress and strain results of RPV and the main pipeline are obtained.The results show that the failure loads of RPV at 600℃,800℃and 1000℃are 1/20,1/50 and 1/100 design loads respectively;The maximum equivalent stress/strain is located near the nozzle;The stress in most areas of the main pipe does not exceed the yield stress of the pipe.This study can provide technical support for structural integrity analysis of RPV under extreme load.

关 键 词：反应堆压力容器(RPV) 蒸汽爆炸 主管道 数值分析 

分 类 号：TL334[核科学技术—核技术及应用]