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Proton irradiation assisted localized corrosion and stress corrosion cracking in 304 nuclear grade stainless steel in simulated primary PWR water
Deng, Ping1,2; Peng, Qunjia1,3; Han, En-Hou1; Ke, Wei1; Sun, Chen4
Corresponding AuthorPeng, Qunjia(pengqunjia@yahoo.com)
2021-02-01
Source PublicationJOURNAL OF MATERIALS SCIENCE & TECHNOLOGY
ISSN1005-0302
Volume65Pages:61-71
AbstractLocalized 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.
KeywordStainless steel AFM TEM High temperature corrosion Stress corrosion
Funding OrganizationInternational Science & Technology Cooperation Program of China ; Essential Research Fund by SNPTC ; Natural Science Foundation of Jiangsu Province
DOI10.1016/j.jmst.2020.04.068
Indexed BySCI
Language英语
Funding ProjectInternational Science & Technology Cooperation Program of China[2014DFA50800] ; Essential Research Fund by SNPTC[2015SN010-007] ; Natural Science Foundation of Jiangsu Province[BK20191178]
WOS Research AreaMaterials Science ; Metallurgy & Metallurgical Engineering
WOS SubjectMaterials Science, Multidisciplinary ; Metallurgy & Metallurgical Engineering
WOS IDWOS:000609935300007
PublisherJOURNAL MATER SCI TECHNOL
Citation statistics
Document Type期刊论文
Identifierhttp://ir.imr.ac.cn/handle/321006/159075
Collection中国科学院金属研究所
Corresponding AuthorPeng, Qunjia
Affiliation1.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
Recommended Citation
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.
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