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核电站主管道不锈钢材料的热老化性能

安英辉 姜冠男 李乾武 史芳杰 杨广宇

理化检验-物理分册2025,Vol.61Issue(11):31-37,7.
理化检验-物理分册2025,Vol.61Issue(11):31-37,7.DOI:10.11973/lhjy-wl240230

核电站主管道不锈钢材料的热老化性能

Thermal aging properties of stainless steel material for main pipeline of nuclear power plant

安英辉 1姜冠男 1李乾武 2史芳杰 2杨广宇2

作者信息

  • 1. 大亚湾核电运营管理有限责任公司,深圳 518124
  • 2. 苏州热工研究院有限公司,苏州 215004
  • 折叠

摘要

Abstract

Taking domestic and imported centrifugal casting austenitic stainless steel as the research object,six batches of samples with different thermal aging time were prepared by accelerated thermal aging method.The mechanical properties of the two materials after thermal aging were compared and analyzed.The microstructure of the samples was systematically characterized by optical microscope,scanning electron microscope and transmission electron microscope.The results show that the performance indexes of the two materials met the requirements of RCCM-M3406 standard.The chemical composition control and microstructure optimization of the main pipeline material would have a significant impact on its thermal aging performance.The formation and development rate of precipitates was not consistent with the decrease rate of mechanical properties of materials.

关键词

核电站/主管道/热老化/显微组织/力学性能

Key words

nuclear power plant/main pipeline/thermal aging/microstructure/mechanical property

分类

矿业与冶金

引用本文复制引用

安英辉,姜冠男,李乾武,史芳杰,杨广宇..核电站主管道不锈钢材料的热老化性能[J].理化检验-物理分册,2025,61(11):31-37,7.

理化检验-物理分册

1001-4012

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