核反应堆压力容器低合金钢与奥氏体不锈钢异种金属焊接研究现状  

Nuclear Reactor Pressure Vessel Low-alloy Steel and Austenitic Stainless Steel Dissimilar Metal Welding Research Status

作　　者：何大明[1] 黄祖来 周利[2,3] 孙舒蕾 HE Daming;HUANG Zulai;ZHOU Li;SUN Shulei(Key Laboratory of Nuclear Reactor System Design Technology,Nuclear Power Institute of China,Chengdu 610213,China;State Key Laboratory of Advanced Welding and Joining,Harbin Institute of Technology,Harbin 150001,China;Shandong Provincial Key Laboratory of Special Welding Technology,Harbin Institute of Technology at Weihai,Weihai 264209,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610213 [2]哈尔滨工业大学先进焊接与连接国家重点实验室,黑龙江哈尔滨150001 [3]哈尔滨工业大学(威海)山东省特种焊接技术重点实验室,山东威海264209

出　　处：《电焊机》2023年第12期7-21,共15页Electric Welding Machine

摘　　要：核电反应堆压力容器是核电站的核心设备之一,其安全性和可靠性对核电站的运行至关重要。在压力容器的制造中,涉及到低合金钢与奥氏体不锈钢的异种金属焊接。针对该异种金属焊接接头存在的组织不均匀性、元素扩散、应力腐蚀裂纹等问题,从焊接填充材料的选择和优化、可能应用的焊接方法、焊后热处理及工艺控制等方向探讨了解决措施与发展方向。为提高此类接头质量和可靠性的研究提供参考,从而确保核电站的安全运行。The nuclear power reactor pressure vessel(RPV)is one of the core equipments in a nuclear power plant(NPP),and its safety and reliability are vital to the operation of the plant.The fabrication of RPV involves the dissimilar metal welding of low-alloy steel to austenitic stainless steel.This paper discusses the problems of organizational inhomogeneity,elemental diffusion,and stress corrosion cracking that exist in this welding.From the selection and optimization of welding filler materials,as well as the possible application of welding methods,post-weld heat treatment,process control,and other directions to discuss possible solutions to welding problems and development directions.To provide a reference for future research to improve the quality and reliability of such joints,thus ensuring the safe operation of NPPs.

关 键 词：反应堆压力容器 异种金属焊接 接头质量 研究现状 

分 类 号：TM623.2[电气工程—电力系统及自动化]