Microstructure, Residual Strain and Stress Corrosion Cracking Behavior in 316L Heat-Affected Zone
查看参考文献35篇
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文摘
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Austenitic stainless steels are usually chosen to make many components of nuclear power plants (NPPs). However, their microstructure in the heat-affected zone (HAZ) will change during the welding process. Some failures of the weld joints, mainly stress corrosion cracking (SCC), have been found to be located in the HAZ. In this research, the microstructure, micro-hardness, residual strain and SCC behavior at different locations of the 316L HAZ cut from a safeend dissimilar metal weld joint were studied. However, traditional optical microscope observation could not find any microstructural difference between the HAZ and the base metal, higher residual strain and micro-hardness, and higher fraction of random high-angle grain boundaries were found in the HAZ than in the base metal when studied by using electron back-scattering diffraction scanning and micro-hardness test. What's more, the residual strain, the microhardness and the fraction of random grain boundaries decreased, while the fraction of coincidence site lattice grain boundaries increased with increasing the distance from the fusion boundary in 316L HAZ. Creviced bent beam test was applied to evaluate the SCC susceptibility at different locations of 316L HAZ and base metal. It was found that the HAZ had higher SCC susceptibility than the base metal and SCC resistance increased when increasing the distance from the fusion boundary in 316L HAZ. |
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来源
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Acta Metallurgica Sinica(English Letters)
,2016,29(9):848-858 【核心库】
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DOI
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10.1007/s40195-016-0461-7
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关键词
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Austenitic stainless steels
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Heat-affected zone
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Microstructure
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EBSD
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Residual strain
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Stress corrosion cracking
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地址
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1.
Institute of Metal Research, Chinese Academy of Sciences, Key Laboratory of Nuclear Materials and Safety Assessment, Chinese Academy of Sciences;;Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Shenyang, 110016
2.
Shanghai Research Center for Weld and Detection Engineering Technique of Nuclear Equipment, Shanghai, 201306
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语种
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英文 |
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文献类型
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研究性论文 |
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ISSN
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1006-7191 |
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学科
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金属学与金属工艺 |
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基金
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上海市科委项目
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国家自然科学基金
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文献收藏号
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CSCD:5804838
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