长寿期运行RPV辐照脆化后结构完整性评定关键技术探讨  

Discussion on the key technology of structure integrity assessment of irradiated RPV in the long-term operation

作　　者：陈明亚[1] 曹昱澎 贺寅彪 孙欣 高红波 林磊[1] 彭群家 陈志林[1] CHEN Mingya;CAO Yupeng;HE Yinbiao;SUN Xin;GAO Hongbo;LIN Lei;PENG Qunjia;CHEN Zhilin(Suzhou Nuclear Power Research Institute,Suzhou 215000,China;Shanghai Nuclear Engineering Research and Design Institute,Shanghai 200233,China;Zhejiang Shuren University,Hangzhou 310015,China)

机构地区：[1]苏州热工研究院有限公司,江苏苏州215000 [2]上海核工程研究设计院有限公司,上海200233 [3]浙江树人大学,杭州310015

出　　处：《压力容器》2023年第2期71-79,86,共10页Pressure Vessel Technology

基　　金：国家重点研发计划项目“核电站重要设备部件先进智能老化监检测技术开发与验证”(2020YFB1901500)。

摘　　要：反应堆压力容器(RPV)辐照脆化后的结构完整性评定(简称“评定”)是核电厂长寿期运行论证中的关键技术难点之一。梳理国内外的相关研究成果,并结合作者团队的研究进展,进行了典型事故瞬态特性分析、RPV评定模型对比、评定准则研究和专用软件开发四方面的关键技术探讨。研究表明,具有重新打压特性的事故瞬态更加危险;不同规范采用了不同方法处理RPV内表面堆焊层问题,其对分析结果存在明显影响;考虑材料的热预应力特性、裂纹止裂性能、尺寸拘束效应等都有益于结构的安全评价;基于通用的商业软件,通过二次开发建立了RPV辐照脆化断裂评定专用软件。Structural integrity assessment(SIA)of embrittled reactor pressure vessel(RPV)is one of the key technical issues in the verification of long-term operation of nuclear power plants(NPPs).By combing the relevant research results and the research advances of the author′s team,the key technologies of typical accident transient characteristic,RPV fracture evaluation model,SIA criteria and development of special software were discussed.The results show that the accident transients with re-pressuring characteristics are more dangerous;and the different treatment methods for cladding in different codes have obvious influence on the results.Considering the thermal prestress characteristics,crack relief performance,size binding effect,etc.of the material are beneficial to the safety evaluation of the structure.Based on the second development of general commercial software,the special software of SIA for RPV has been developed.

关 键 词：反应堆压力容器 辐照脆化 断裂评定 长寿期运行 

分 类 号：TH49[机械工程—机械制造及自动化] TL351.6[核科学技术—核技术及应用] TB121[理学—工程力学]