核电机组堆内构件螺栓断裂事故分析与改进研究  

Analysis and Improvement for the Bolt Fracture in Reactor Vessel Internals of Nuclear Power Plant

作　　者：王庆田[1] 胡朝威[1] 李燕[1] 张翼[1] 李浩[1] 吴水洁 陈忻 WANG Qing-tian;HU Chao-wei;LI Yan;ZHANG Yi;LI Hao;WU Shui-jie;CHEN Xin(Key Reactor System Design Technology Laboratory,Nuclear Power Institute of China?Chengdu?Sichuan Prov.610041,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，四川 成都 610041

出　　处：《中国核电》2018年第4期481-487,共7页China Nuclear Power

摘　　要：介绍了阳江核电站堆内构件二次支承与仪表套管组件螺栓断裂脱落事故,以及由螺栓脱落事故导致的对一回路主设备造成的损伤。从设计、制造、安装和运行等各方面,排查、分析了螺栓断裂产生的原因。根据原因分析结果,提出了相应的改进措施。这些改进措施,对于后续M310堆型核电站以及包括"华龙一号"、欧洲先进压水堆EPR以及AP1000为代表的三代核电站的现场安装和焊接,都具有重要的参考和借鉴意义。The paper introduces the fracture accident happened in the bottom mounted instrumentation and secondary core support assembly in RVI of Unit 2 of Yangjiang NPP.Besides,the paper also introduces the dam-age caused by the bolt fracture to the primary circuit equipment.The paper analyses the cause of fracture interms of design,manufacture,mounting and operation,and puts forwards some improvement measures.Thekey measures put forward by this paper can be used as reference for the welding on site for the following reactorinternals,such as ACP1000,EPR and AP1000 and so on.

关 键 词：阳江核电站 堆内构件 螺栓 断裂 原因分析 

分 类 号：TM623[电气工程—电力系统及自动化]