反应堆压力容器压力-温度限值曲线分析方法研究  

Study on the Pressure-Temperature Limit Curve Analysis Method for the Reactor Pressure Vessel

作　　者：吴炳洋 傅孝龙[1] 张丽屏[1] 卢岳川[1] 石凯凯[1] WU Bingyang;FU Xiaolong;ZHANG Liping;LU Yuechuan;SHI Kaikai(Key Laboratory on Reactor System Design Technology,Nuclear Power Institute of China,Chengdu,Sichuan Prov.610200,China)

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,四川成都610213

出　　处：《中国核电》2024年第4期569-576,共8页China Nuclear Power

摘　　要：核电厂在反应堆启、停堆过程中必须将压力和温度控制在一定范围内,即压力-温度限值曲线(P-T曲线)所允许的范围内,以防止反应堆压力容器发生脆性开裂。本文论述了反应堆压力容器P-T曲线制定的防脆断设计的基础理论,总结了EJ/T 918-94规范和RCC-M 2007规范中关于P-T曲线的计算方法和分析流程,采用ANSYS APDL编程实现了P-T曲线的自动分析,并对RCC-M 2007规范中的P-T计算分析方法进行了完善,对计算结果进行了对比分析,研究表明EJ/T 918的计算结果过于保守。In order to prevent the brittle fracture during nuclear power plant startup and shutdown process,the pressure and temperature in the reactor pressure vessel should be kept under the pressure-temperature(P-T)limit curve.This paper discusses the basic theory of anti-brittle fracture design for the formulation of the P-T limit curve of the reactor pressure vessel,summarizes the calculation method and analysis process of the P-T limit curve in EJ/T 918-94 code and RCC-M 2007 code,realizes the calculation and analysis of the P-T limit curve by using ANSYS APDL programming,improves the method in the RCC-M code,and finally carries out comparison and analysis for the P-T limit curve based on different code.The study shows that the calculation results based on EJ/T918 are too conservative.

关 键 词：压力-温度限值曲线 脆性断裂 反应堆压力容器 

分 类 号：TM623[电气工程—电力系统及自动化]