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 Author | Peng, Qunjia(pengqunjia@yahoo.com) |
2021-02-01 | |
Source Publication | JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY
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ISSN | 1005-0302 |
Volume | 65Pages:61-71 |
Abstract | 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. |
Keyword | Stainless steel AFM TEM High temperature corrosion Stress corrosion |
Funding Organization | 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 |
Indexed By | SCI |
Language | 英语 |
Funding Project | International Science & Technology Cooperation Program of China[2014DFA50800] ; Essential Research Fund by SNPTC[2015SN010-007] ; Natural Science Foundation of Jiangsu Province[BK20191178] |
WOS Research Area | Materials Science ; Metallurgy & Metallurgical Engineering |
WOS Subject | Materials Science, Multidisciplinary ; Metallurgy & Metallurgical Engineering |
WOS ID | WOS:000609935300007 |
Publisher | JOURNAL MATER SCI TECHNOL |
Citation statistics | |
Document Type | 期刊论文 |
Identifier | http://ir.imr.ac.cn/handle/321006/159075 |
Collection | 中国科学院金属研究所 |
Corresponding Author | Peng, Qunjia |
Affiliation | 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 |
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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