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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

何大明 黄祖来 周利 孙舒蕾

电焊机2023,Vol.53Issue(12):7-21,15.
电焊机2023,Vol.53Issue(12):7-21,15.DOI:10.7512/j.issn.1001-2303.2023.12.02

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

何大明 1黄祖来 2周利 2孙舒蕾2

作者信息

  • 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||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
  • 折叠

摘要

Abstract

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 weld-ing of low-alloy steel to austenitic stainless steel.This paper discusses the problems of organizational inhomogeneity,el-emental 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 re-search 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

Key words

reactor pressure vessel/dissimilar metals welding/joint quality/research status

分类

信息技术与安全科学

引用本文复制引用

何大明,黄祖来,周利,孙舒蕾..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[J].电焊机,2023,53(12):7-21,15.

电焊机

OACSTPCD

1001-2303

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