反应堆压力容器堆芯筒体快速断裂分析

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Analysis of Fast Fracture of Core Region of RPV

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power institute of China, Chengdu, 610041, China

摘要: 反应堆压力容器的堆芯筒体受中子辐照最高,是辐照脆化敏感的关键部位。为防止堆芯筒体的快速断裂,在核电工程设计中有必要对该部位进行断裂力学分析,采用法国《压水堆核岛机械设备设计和建造准则》(RCC-M)规定的2种断裂力学分析方法对某核电工程的压力容器进行详细的快速断裂力学分析。分析结果表明,反应堆压力容器堆芯筒体在运行过程中不会发生快速断裂。
- 堆芯筒体 /
- 反应堆压力容器 /
- 快速断裂
Abstract: The core region of reactor pressure vessel is the main part irradiated by the core,since irradiation raises the nil ductility transition temperature.This increases the sensibility to fast fracture.To prevent the vessel fast fracture of vessel,the fast fracture mechanics analysis is necessary in the design of reactor vessel.In the paper,fast fracture mechanics analysis was performed using the first method and the second method for RPV according to RCC-M.The analysis results met the allowable limits.
- Core region /
- RPV /
- Fast fracture