针对役前检查发现的秦山核电二期扩建工程4号机组反应堆压力容器堆焊层缺陷，采用法国核岛设备设计和建造规则协会(AFCEN)制定的?压水堆核岛机械设备在役检查规则(RSE-M)?对其进行了断裂力学分析与评定，并与?ASME锅炉及压力容器规范(ASME B&PVC)：第Ⅺ卷?分析与评定结果进行了比较。结果表明：此工作形成了RSE-M规范断裂力学分析与缺陷评定的工程应用方法，与ASME方法相比此工程应用方法具有一定的保守性；提出的裂纹尖端应力强度因子K I具体计算方法，弥补了RSE-M以及ASME B&PVC第Ⅺ卷中断裂力学相关内容的缺失。
Using the In-Service Inspection Rules for Mechanical Components of PWR Nuclear Islands (RSE-M)issued by AFCEN,the fracture mechanics analysis and evaluation of the defect,which was found by pre-service examination on the reactor pressure vessel cladding of unit 4 for Qinshan nuclear power phase Ⅱ expansion proj ect, was analyzed and compared to the analysis and evaluation results using ASME Boiler and Pressure Vessel Code (ASME B&PVC ) Section Ⅺ.The results show that the engineering application method of RSE-M fracture mechanics analysis and evaluation of defects was developed,and it showed a relatively conservative comparing to the method of ASME.The calculation method of crack tip stress intensity factor KI was proposed,which can make up for the lack of relevant content of the fracture mechanics in RSE-M and ASME B&PVC Section Ⅺ.
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