Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant: Microstructure and stress corrosion cracking

被引：17
作者：
Wu, Bin [1 ,2 ]
Ming, Hongliang [1 ,2 ]
Meng, Fanjiang [3 ]
Li, Yifeng [4 ]
He, Guangqing [5 ,6 ]
Wang, Jianqiu [1 ,2 ]
Han, En-Hou [2 ]
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 110016, Peoples R China
[3] Shanghai Nucl Engn Res & Design Inst Ltd Co, Shanghai 200233, Peoples R China
[4] Shanghai Univ, Instrumental Anal & Res Ctr, Shanghai 200444, Peoples R China
[5] Fudan Univ, Dept Mat Sci, Shanghai 200433, Peoples R China
[6] Shanghai Elect Nucl Power Equipment Co Ltd, Shanghai 201306, Peoples R China
来源：
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY | 2022年 / 113卷
基金：
中国国家自然科学基金;
关键词：
Alloy; 690TT; Scratch; Surface; Stress corrosion; High temperature corrosion; Intergranular corrosion; PRESSURIZED-WATER REACTORS; QUANTITATIVE ASSESSMENT; STAINLESS-STEEL; SECONDARY-SIDE; BEHAVIOR; RESISTANCE; SUBMODES; STRAIN;
D O I：
10.1016/j.jmst.2021.11.009
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
Alloy 690TT tube samples with different scratch depths were repaired by grinding treatments using abrasive papers of two different particle sizes. The microstructure and stress corrosion cracking (SCC) behavior were studied in detail. During grinding, the plastic accumulation zone vulnerable to SCC was removed. Meanwhile, some residual slip steps remained in the scratched area. Corrosion tests lasting 10 0 0, 20 0 0, 30 0 0, and 40 0 0 h show that the sensitivity and risk of SCC in the scratched area are decreased by grinding. Treatment using abrasive particles of a smaller size is more effective. Nevertheless, deep scratches remained hazardous even after the grinding. (c) 2022 Published by Elsevier Ltd on behalf of The editorial office of Journal of Materials Science & Technology.
引用
收藏
页码：229 / 245
页数：17
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