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

页数：17

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