碳含量超标情况下的反应堆压力容器快速断裂评价方法研究  

Study on Fast Fracture Evaluation Method for Reactor Pressure Vessel with Excessive Carbon Content

作　　者：苏东川[1] 谢海[1] 张毅雄[1] 崔怀明[1] 吴琳[1] Su Dongchuan;Xie Hai;Zhang Yixiong;Cui Huaiming;Wu Lin(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,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,成都610213

出　　处：《核动力工程》2021年第4期282-288,共7页Nuclear Power Engineering

摘　　要：按照RCC-M规范对设备进行快速断裂评价时,材料的初始无延性转变温度是重要的输入条件之一。材料中的碳含量超标会影响材料初始无延性转变温度,但目前2者之间还没有定量关系。当反应堆压力容器(RPV)出现碳含量超标时,为保证结构完整性,必须在缺乏定量关系的情况下完成结构的快速断裂分析。本研究对碳含量超标情况下的反应堆压力容器的快速断裂评价方法进行了研究,并以发生碳含量超标的反应堆压力容器堆芯段筒体为例,考虑了筒体的缺陷修复情况,通过反算满足规范要求的最高初始无延性转变温度,对反应堆压力容器堆芯段筒体的快速断裂情况进行了分析评估。该方法可为碳含量超标的压力容器运行和在役检测提供技术支持。The initial non-ductile transition temperature is an important input parameter in fast fracture evaluation according to the RCC-M code.The initial non-ductile transition temperature(RTNDT)will be affected by the carbon content,but there is no quantitative relationship between them.When the carbon content of the reactor pressure vessel exceeds the standard,it is necessary to complete the fast fracture evaluation without quantitative relationship to ensure the integrality of RPV.In this paper,the evaluation method of the fast fracture of RPV with excessive carbon content is studied.Taking the RPV core barrel with excessive carbon content as an example,the defect repair is considered,and the fast fracture analysis and evaluation are carried out by calculating the maximum initial non-ductile transition temperature.This method can support the operation and the in-service inspection of the pressure vessels with excessive carbon content.

关 键 词：反应堆压力容器(RPV) 快速断裂 初始无延性转变温度 碳含量 

分 类 号：TL334[核科学技术—核技术及应用]