秦山核电二期工程冷却剂系统管件应力分析  

Stress Analyses of Some Pipe Components and Welding-lines of RCS in Qinshan Phase II NPP Project

作　　者：陈学德[1] 陈晓舟[1] 崔赪昕[1] 

机构地区：[1]中国核动力研究设计院,成都610041

出　　处：《核动力工程》2003年第z1期91-95,共5页Nuclear Power Engineering

摘　　要：用RCC-M B3650提供的简化分析方法及ANSYS程序,计算了秦山核电二期工程冷却剂系统接管嘴和焊缝的各类应力强度,分析了管道沿壁厚方向的瞬态温度场;用RCC-M提供的方法计算线性温差ΔT1和非线性温差ΔT2。结果表明,部分管件不满足RCC-M的方程(13)和热棘轮限制。This paper presents stress analyses of some pipe components and welding-lines of the reactor coolant system in Qinshan Phase II NPP Project. According to the RCC-M code, a simplified analysis method was used to calculate all kinds of stress intensity of these pipe components and welding-lines. Further more, the transient thermal-fields along the radius direction were obtained by using the ANSYS FEM program. The analyses results show that the stress of some components exceeds the heat ratchet limit and does not satisfy the requirements of the RCC-M code.

关 键 词：冷却剂系统 管件 应力分析 

分 类 号：TM623[电气工程—电力系统及自动化] O343[理学—固体力学]