反应堆压力容器缺陷的断裂评定  

Fracture assessment for reactor pressure vessel flaw

作　　者：郑斌[1] 

机构地区：[1]中国核动力研究设计院反应堆系统设计重点试验室,成都610041

出　　处：《核技术》2013年第4期131-134,共4页Nuclear Techniques

摘　　要：某反应堆压力容器在役UT检查时发现一处缺陷,为确保RPV在服役期限内的结构完整性,有必要进行RPV缺陷的断裂力学分析研究。根据ASME规范,将该缺陷假定为裂纹深度为10.1 mm的环向内表面裂纹,并进行了断裂力学计算及评价。分析内容主要包括计算疲劳裂纹扩展量、评价各种工况下的应力强度因子,载荷为瞬态的温度波动、压力以及焊接残余应力。评价工况包括正常及扰动工况、紧急工况、事故工况。研究结果表明,正常及扰动工况瞬态载荷对RPV筒体浅层内表面裂纹的疲劳扩展作用不明显,40年寿期末的疲劳裂纹扩展量约为0.228 mm。各工况下的应力强度因子均满足规范要求,含缺陷的反应堆压力容器可以继续服役,无需修补。Background： A flaw is discovered by ultrasonic test at reactor pressure vessel during the service. Purpose： In order to insure the structural integrality of RPV, it is necessary to perform the fracture analysis for RPV flaw. Methods： According to ASME rule, fracture analysis is performed, which the flaw is assumed as a circumferential surface crack and crack depth is 10.1 mm. The analysis work contains the calculation of fatigue crack growth and the assessment of stress intensity factor under several category conditions. The loads are the temperature fluctuation, pressure and weld residual stress. The concerned category conditions include normal and upset conditions, emergency conditions, and faulted conditions. Results： The analysis results show that normal and upset conditions transient loading has little effect on the fatigue crack growth of low inner surface crack. The fatigue crack growth is about 0.228 mm at the end of 40 years service life. Conclusions： The stress intensity factor results of all conditions satisfy the requirement of ASME Rule. The RPV with flaw can continue service without repair.

关 键 词：应力强度因子 压力容器 断裂 评定 

分 类 号：TL351.6[核科学技术—核技术及应用]