Proton irradiation assisted localized corrosion and stress corrosion cracking in 304 nuclear grade stainless steel in simulated primary PWR water

doi:10.1016/j.jmst.2020.04.068

IMR OpenIR

	Proton irradiation assisted localized corrosion and stress corrosion cracking in 304 nuclear grade stainless steel in simulated primary PWR water
	Deng, Ping 1,2; Peng, Qunjia 1,3; Han, En-Hou 1; Ke, Wei 1; Sun, Chen 4
通讯作者	Peng, Qunjia(pengqunjia@yahoo.com)
	2021-02-01
发表期刊	JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY
ISSN	1005-0302
卷号	65 页码:61-71
摘要	Localized deformation and corrosion in irradiated 304 nuclear grade stainless steel in simulated primary water were investigated. The investigation was conducted by comparing the deformation structure, the oxide scale formed at the deformation structure, and their correlation with cracking. The results revealed that increasing the irradiation dose promoted localized corrosion at the slip step and grain boundary, which was primarily attributed to the strain concentration induced by enhanced localized deformation and depletion of Cr at grain boundary. Further, a synergic effect of the enhanced localized deformation and localized corrosion at the slip step and grain boundary caused a higher cracking susceptibility of the irradiated steel. (C) 2021 Published by Elsevier Ltd on behalf of The editorial office of Journal of Materials Science & Technology.
关键词	Stainless steel AFM TEM High temperature corrosion Stress corrosion
资助者	International Science & Technology Cooperation Program of China ; Essential Research Fund by SNPTC ; Natural Science Foundation of Jiangsu Province
DOI	10.1016/j.jmst.2020.04.068
收录类别	SCI
语种	英语
资助项目	International Science & Technology Cooperation Program of China[2014DFA50800] ; Essential Research Fund by SNPTC[2015SN010-007] ; Natural Science Foundation of Jiangsu Province[BK20191178]
WOS研究方向	Materials Science ; Metallurgy & Metallurgical Engineering
WOS类目	Materials Science, Multidisciplinary ; Metallurgy & Metallurgical Engineering
WOS记录号	WOS:000609935300007
出版者	JOURNAL MATER SCI TECHNOL
引用统计	被引频次：22[WOS] [WOS记录] [WOS相关记录]
文献类型	期刊论文
条目标识符	http://ir.imr.ac.cn/handle/321006/159075
专题	中国科学院金属研究所
通讯作者	Peng, Qunjia
作者单位	1.Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China 2.Nucl Power Inst China, Chengdu 610213, Peoples R China 3.Suzhou Nucl Power Res Inst, Suzhou 215004, Peoples R China 4.State Power Investment Corp Res Inst, Beijing 102209, Peoples R China
推荐引用方式 GB/T 7714	Deng, Ping,Peng, Qunjia,Han, En-Hou,et al. Proton irradiation assisted localized corrosion and stress corrosion cracking in 304 nuclear grade stainless steel in simulated primary PWR water[J]. JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY,2021,65:61-71.
APA	Deng, Ping,Peng, Qunjia,Han, En-Hou,Ke, Wei,&Sun, Chen.(2021).Proton irradiation assisted localized corrosion and stress corrosion cracking in 304 nuclear grade stainless steel in simulated primary PWR water.JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY,65,61-71.
MLA	Deng, Ping,et al."Proton irradiation assisted localized corrosion and stress corrosion cracking in 304 nuclear grade stainless steel in simulated primary PWR water".JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY 65(2021):61-71.