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非能动核电站钢制安全壳焊接及焊后热处理探讨

朱瑞峰 张俊宝 吴崇志 丛大志

压力容器2025,Vol.42Issue(6):74-81,8.
压力容器2025,Vol.42Issue(6):74-81,8.DOI:10.3969/j.issn.1001-4837.2025.06.009

非能动核电站钢制安全壳焊接及焊后热处理探讨

Discussion on welding and PWHT of steel containment vessels for passive nuclear power plants

朱瑞峰 1张俊宝 1吴崇志 2丛大志1

作者信息

  • 1. 上海核工程研究设计院股份有限公司,上海 200233||核电关键材料全国重点实验室,上海 200233
  • 2. 上海核工程研究设计院股份有限公司,上海 200233
  • 折叠

摘要

Abstract

To address the difficulties in welding process optimization and quality control during the manufacturing of steel containment vessels,this paper systematically discusses key manufacturing steps such as weld jurisdiction determination,welding preheating,process selection,and post-weld heat treatment based on the analysis of engineering practices and relevant standards and codes.The results show that due to differences in carbon equivalent,SA-738 Gr.B steel requires customized preheating schemes;using shielded metal arc welding for the root pass combined with mechanized welding for filling and capping passes can ensure quality while improving efficiency;The use of tooling fixtures can effectively control deformation during post-weld heat treatment,and exemption from heat treatment within the allowable range of standards is more economical.The study provides an important reference for the optimization of manufacturing processes for nuclear power plant steel containment vessels,and the related methodology can also be extended to the manufacturing of other safety-class equipment.

关键词

钢制安全壳/焊缝管辖/焊接预热/焊接工艺/焊后热处理

Key words

steel containment vessel/weld jurisdiction/welding preheating/welding process/post-weld heat treatment

分类

机械工程

引用本文复制引用

朱瑞峰,张俊宝,吴崇志,丛大志..非能动核电站钢制安全壳焊接及焊后热处理探讨[J].压力容器,2025,42(6):74-81,8.

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