基于RCC-M与ASME标准的反应堆压力容器快速断裂分析方法的差异性研究  

Research on Fast-fracture Analysis Methods Differences of Reactor Pressure Vessel Based on RCC-M and ASME Standard

作　　者：杨成 王建军 谭晓敏 Yang Cheng;Wang Jianjun;Tan Xiaomin(Nuclear Power Operations Research Institute,Shanghai 200120)

机构地区：[1]核电运行研究(上海)有限公司,上海200120

出　　处：《中国特种设备安全》2025年第4期1-7,共7页China Special Equipment Safety

摘　　要：快速断裂是反应堆压力容器设计和运行在役监督必须关注的失效模式,我国常用的美系ASME和法系RCC-M规范对快速断裂分析的内容存在差异。以美系设计规范ASMEⅢ卷2004版和法系设计规范RCC-M2007版为研究对象,分析2个规范定义的快速断裂分析方法差异性,从初始假想裂纹尺寸、应力强度因子计算方法和评判准则3个方面开展对比研究,结合某堆型RPV堆芯段筒体计算案例进行论证,定量探究2个标准在快速断裂分析方法上的差异性,以为不同标准体系下的运行在役监督策略优化提供参考。Fast-fracture failure is a failure mode that must be paid attention to during design and in-service surveillance stage of reactor pressure vessel.There are differences in the content of fast-fracture analysis between American ASME and French RCC-M codes commonly used in China.The differences of the fast-fracture analysis methods defined by the two codes are briefly described by taking the American design code ASME III Volume 2004 edition and the French design code RCC-M 2007 edition as the research objects.The comparative study is carried out from three aspects:initial hypothetical crack size,calculation method of stress intensity factor and requirements of service limit.Combined with the typical case of a RPV core section cylinder,the differences of the two standards in fast-fracture analysis methods are quantitatively explored,which provides a reference for the optimization of in-service surveillance strategy in the subsequent operation stage.

关 键 词：ASME RCC-M 快速断裂分析 安全裕量 反应堆压力容器 

分 类 号：X933.4[环境科学与工程—安全科学]