在役核电站蒸汽发生器返修堵管自动焊工艺研究  

Study on automatic welding process of repair the blocking pipe for steam generator in in-service nuclear power plant

作　　者：周政 方江 赵亮 张晓冬 马威 张国范 王登星 ZHOU Zheng;FANG Jiang;ZHAO Liang;ZHANG Xiaodong;MA Wei;ZHANG Guofan;WANG Dengxing(China Nuclear Power Operation Technology Co.,Ltd.,Wuhan 430000,Hubei,China;CNNC Nuclear Power Operations Management Co.,Ltd.,Haiyan 430000,Zhejiang,China;Nuclear Industry Research and Engineering Co.,Ltd.,Beijing 101300,China)

机构地区：[1]中核武汉核电运行技术股份有限公司,湖北武汉430000 [2]中核核电运行管理有限公司,浙江海盐314300 [3]核工业工程研究设计有限公司,北京101300

出　　处：《金属加工(热加工)》2025年第4期111-117,共7页MW Metal Forming

摘　　要：为解决传热管因发生破损而导致放射性介质从一回路泄漏的问题,提出了一种蒸汽发生器传热管自动焊接堵管的工艺,采用堵头“自熔环”结构及分段式自熔焊接方法,通过对传热管堵管返修焊接参数的调整及热输入控制,得到了一套最优的堵管返修自动焊工艺参数,该套工艺下的堵管焊缝具有良好的根部熔合情况、表面成形效果及力学性能。In order to prevent leakage of radioactive material from the primary circuit due to the damage of heat transfer tubes,an automatic welding technology for repairing these tubes in steam generator is proposed in this paper.Using the “self-melting ring” structure and the segmented welding approach,a set of automatic welding process parameters are obtained by optimizing the welding parameters and the heat input.Through this process,the welds of the tubes have good root fusion,surface forming and mechanical properties.

关 键 词：在役核电 返修 蒸汽发生器 传热管 堵头 自动焊工艺 

分 类 号：TG457.2[金属学及工艺—焊接]