Effect of post-irradiation annealing on microstructure and corrosion of proton-irradiated 308L stainless steel weld metal

被引：18
|
作者：
Lin, Xiaodong [1 ,2 ]
Han, En-Hou [1 ]
Peng, Qunjia [1 ,3 ]
Ke, Wei [1 ]
Jiao, Zhijie [4 ]
机构：
[1] Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China
[2] Univ Sci & Technol China, Sch Mat Sci & Engn, Shenyang 110016, Peoples R China
[3] Suzhou Nucl Power Res Inst, Suzhou 215004, Peoples R China
[4] Univ Michigan, Dept Nucl Engn & Radiol Sci, Ann Arbor, MI 48109 USA
来源：
CORROSION SCIENCE | 2020年 / 175卷
基金：
中国国家自然科学基金;
关键词：
Stainless steel; TEM; High temperature corrosion; Segregation; Welding; PWR PRIMARY WATER; RADIATION-INDUCED SEGREGATION; OXIDE-FILM; G-PHASE; IN-SITU; INDUCED PRECIPITATION; MECHANICAL-PROPERTIES; DEFECT STRUCTURE; STRESS; EVOLUTION;
D O I：
10.1016/j.corsci.2020.108887
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The effect of post-irradiation annealing (PIA) at 550 degrees C for 1 h on microstructure and corrosion of proton-irradiated 308L stainless steel weld metal was investigated. After PIA, growth of voids and Frank loops in austenite occurred, whereas Ni/Si-rich clusters in austenite, spinodal decomposition and G-phase in delta-ferrite, and segregation at grain boundary were removed. Corrosion experiments showed that the inner oxide thickness of austenite was increased by PIA, while the oxide scale on delta-ferrite was unaffected. In addition, localized corrosion was not observed along the grain boundary and carbide-free phase boundary, while it still remained along the carbide-containing phase boundary.
引用
收藏
页数：17
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