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Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect

文献类型：期刊论文

作者Wu, Bin5,6; Ming, Hongliang5,6; Zhang, Zhiming4; Meng, Fanjiang3; He, Guangqing1,2; Wang, Jianqiu4,5,6; Han, En-Hou4,6
刊名JOURNAL OF NUCLEAR MATERIALS
出版日期2022-05-01
卷号563页码:14
关键词Alloy 690TT Tube expansion Internal bulge defect Stress corrosion cracking Intergranular corrosion High temperature corrosion
ISSN号0022-3115
DOI10.1016/j.jnucmat.2022.153629
通讯作者Ming, Hongliang(hlming12s@imr.ac.cn) ; Meng, Fanjiang(mengfanjiang@snerdi.com.cn)
英文摘要S C Alloy 690TT tube samples with different sizes of internal bulge defect (IBD) are prepared by actual hydraulic tube expansion in field and their microstructure and stress corrosion cracking (SCC) behavior are studied in detail. The hardening level and residual strain increase as moving from the original area of the tube to the bulged area, and so as for the increasing of deformation sizes. Corrosion test with a duration of 20 0 0 h shows that the IBD area has higher SCC sensitivity than the original tube. In addition, IBD with larger size is more sensitive to SCC. (c) 2022 Elsevier B.V. All rights reserved.
资助项目Youth Innovation Promo-tion Association CAS[2022187] ; National Natural Science Foun-dation of China[51771211] ; National Key RD Program[2019YFB1900904] ; CAS Key lab-oratory of Nuclear Materials and Safety Assessment (Instituteof Metal Research, Chinese Academy of Sciences , China)[2021NMSAKF01] ; CAS Key lab-oratory of Nuclear Materials and Safety Assessment (Instituteof Metal Research, Chinese Academy of Sciences , China)[2022NMSAKF03]
WOS研究方向Materials Science ; Nuclear Science & Technology
语种英语
WOS记录号WOS:000793200400006
出版者ELSEVIER
资助机构Youth Innovation Promo-tion Association CAS ; National Natural Science Foun-dation of China ; National Key RD Program ; CAS Key lab-oratory of Nuclear Materials and Safety Assessment (Instituteof Metal Research, Chinese Academy of Sciences , China)
源URL[http://ir.imr.ac.cn/handle/321006/173929]  
专题金属研究所_中国科学院金属研究所
通讯作者Ming, Hongliang; Meng, Fanjiang
作者单位1.Fudan Univ, Dept Mat Sci, Shanghai 200433, Peoples R China
2.Shanghai Elect Nucl Power Equipment Co Ltd, Shanghai 201306, Peoples R China
3.Shanghai Nucl Engn Res & Design Inst Ltd Co, Shanghai 200233, Peoples R China
4.Inst Corros Sci & Technol, Guangzhou 510530, Peoples R China
5.Univ Sci & Technol China, Sch Mat Sci & Engn, Shenyang 110016, Peoples R China
6.Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China
推荐引用方式
GB/T 7714		 Wu, Bin,Ming, Hongliang,Zhang, Zhiming,et al. Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect[J]. JOURNAL OF NUCLEAR MATERIALS,2022,563:14.
APA Wu, Bin.,Ming, Hongliang.,Zhang, Zhiming.,Meng, Fanjiang.,He, Guangqing.,...&Han, En-Hou.(2022).Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect.JOURNAL OF NUCLEAR MATERIALS,563,14.
MLA Wu, Bin,et al."Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect".JOURNAL OF NUCLEAR MATERIALS 563(2022):14.

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来源：金属研究所

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