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

doi:10.1016/j.jmst.2021.11.009

CORC > 金属研究所 > 中国科学院金属研究所

	Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant: Microstructure and stress corrosion cracking
	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
刊名	JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY
	2022-06-20
卷号	113 页码:229-245
关键词	Alloy 690TT Scratch Surface Stress corrosion High temperature corrosion Intergranular corrosion
ISSN号	1005-0302
DOI	10.1016/j.jmst.2021.11.009
通讯作者	Ming, Hongliang(hlming12s@imr.ac.cn) ; Meng, Fanjiang(mengfanjiang@snerdi.com.cn)
英文摘要	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.
资助项目	National Natural Science Foundation of China[51771211] ; National Key RD Program[2019YFB1900904] ; CAS Key laboratory of Nuclear Materials and Safety Assessment (Institute of Metal Research, Chinese Academy of Sciences, China)[2021NMSAKF01]
WOS研究方向	Materials Science ; Metallurgy & Metallurgical Engineering
语种	英语
出版者	JOURNAL MATER SCI TECHNOL
WOS记录号	WOS:000788133000005
资助机构	National Natural Science Foundation of China ; National Key RD Program ; CAS Key laboratory of Nuclear Materials and Safety Assessment (Institute of Metal Research, Chinese Academy of Sciences, China)
内容类型	期刊论文
源URL	[http://ir.imr.ac.cn/handle/321006/172500]
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.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
推荐引用方式 GB/T 7714	Wu, Bin,Ming, Hongliang,Meng, Fanjiang,et al. Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant: Microstructure and stress corrosion cracking[J]. JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY,2022,113:229-245.
APA	Wu, Bin.,Ming, Hongliang.,Meng, Fanjiang.,Li, Yifeng.,He, Guangqing.,...&Han, En-Hou.(2022).Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant: Microstructure and stress corrosion cracking.JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY,113,229-245.
MLA	Wu, Bin,et al."Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant: Microstructure and stress corrosion cracking".JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY 113(2022):229-245.