Stress corrosion behavior of scratched Alloy 690TT steam generator tube in chlorine-containing high-temperature pressurized water

被引:7
|
作者
Wu, Bin [1 ,2 ,3 ]
Meng, Fanjiang [1 ]
Zhang, Zhiming [4 ]
Li, Rongbo [1 ,3 ]
Ming, Hongliang [2 ,3 ]
Wang, Jianqiu [1 ,2 ,3 ,4 ]
Han, En-Hou [2 ,3 ,4 ]
机构
[1] Univ Sci & Technol China, Sch Mat Sci & Engn, Shenyang 110016, Peoples R China
[2] Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang, Peoples R China
[3] Shanghai Nucl Engn Res & Design Inst Ltd Co, Shanghai 200233, Peoples R China
[4] Inst Corros Sci & Technol, Guangzhou, Peoples R China
来源
基金
中国国家自然科学基金;
关键词
Alloy; 690TT; chloride ions; high-temperature pressurized water; scratch; stress corrosion cracking; HEAT-AFFECTED ZONE; MICROSTRUCTURAL CHARACTERIZATION; QUANTITATIVE ASSESSMENT; PASSIVITY-DEGRADATION; SECONDARY-SIDE; CRACKING; DEFORMATION; RESISTANCE; SUBMODES; REACTORS;
D O I
10.1002/maco.202213215
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Alloy 690TT tube samples with six different scratch depths are prepared for immersion test in high-temperature pressurized water containing chloride ions (Cl-) at 300 degrees C. An immersion test with a duration of 1000 h shows that the scratched area with higher scratch depth has higher stress corrosion cracking sensitivity. In chloride-containing solution, Cl- erodes preferentially into the scratched area through the weak sites such as slip bands and deformed grain boundaries, and this process is continuously promoted with the assistance of higher residual strain in this area.
引用
收藏
页码:1563 / 1574
页数:12
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