Crevice corrosion behavior of Alloy 690 in high-temperature water | |
Ning, Fangqiang1,2; Wu, Xinqiang1; Tan, Jibo1 | |
Corresponding Author | Wu, Xinqiang(xqwu@imr.ac.cn) |
2019-03-01 | |
Source Publication | JOURNAL OF NUCLEAR MATERIALS
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ISSN | 0022-3115 |
Volume | 515Pages:326-337 |
Abstract | Characterizations of oxide films formed on Alloy 690 during crevice corrosion in 290 degrees C pure water were investigated. It was found that different hydrochemistry conditions and potential drop affected the development of oxide films within the crevice. The thick oxide film formed at crevice mouth mainly consisted of compact NiO and NiFe2O4 due to the precipitation of Ni2+ and Fe2+, while the thin oxide film formed within the crevice mainly consisted of an outer layer of Cr(OH)(3) and (Fe, Ni)Cr2O4, and a continuous inner layer of Cr2O3, which was attributed to the hydrolysis of Cr3+ and decreased the pH value of the crevice solution. Possible mechanisms of crevice corrosion and growth of the oxide films at different sites along the crevice in high-temperature water are discussed. (C) 2019 Elsevier B.V. All rights reserved. |
Keyword | Alloy Crevice corrosion Oxidation High-temperature corrosion XPS |
Funding Organization | National Natural Science Foundation of China ; National Science and Technology Major Project ; Key Programs of the Chinese Academy of Sciences [Research on the Development of Nuclear Power Materials and Service Security Technology] ; Innovation Fund of Institute of Metal Research, Chinese Academy of Sciences |
DOI | 10.1016/j.jnucmat.2018.12.050 |
Indexed By | SCI |
Language | 英语 |
Funding Project | National Natural Science Foundation of China[51671201] ; National Science and Technology Major Project[2017ZX06002003-004-002] ; Key Programs of the Chinese Academy of Sciences [Research on the Development of Nuclear Power Materials and Service Security Technology][ZDRW-CN-2017-1] ; Innovation Fund of Institute of Metal Research, Chinese Academy of Sciences[SCJJ-2013-ZD-02] |
WOS Research Area | Materials Science ; Nuclear Science & Technology |
WOS Subject | Materials Science, Multidisciplinary ; Nuclear Science & Technology |
WOS ID | WOS:000456805800031 |
Publisher | ELSEVIER SCIENCE BV |
Citation statistics | |
Document Type | 期刊论文 |
Identifier | http://ir.imr.ac.cn/handle/321006/131328 |
Collection | 中国科学院金属研究所 |
Corresponding Author | Wu, Xinqiang |
Affiliation | 1.Chinese Acad Sci, CAS Key Lab Nucl Mat & Safety Assessment, Liaoning Key Lab Safety & Assessment Tech Nucl Ma, Inst Met Res, Shenyang 110016, Liaoning, Peoples R China 2.Univ Sci & Technol China, Sch Mat Sci & Engn, Hefei 230026, Anhui, Peoples R China |
Recommended Citation GB/T 7714 | Ning, Fangqiang,Wu, Xinqiang,Tan, Jibo. Crevice corrosion behavior of Alloy 690 in high-temperature water[J]. JOURNAL OF NUCLEAR MATERIALS,2019,515:326-337. |
APA | Ning, Fangqiang,Wu, Xinqiang,&Tan, Jibo.(2019).Crevice corrosion behavior of Alloy 690 in high-temperature water.JOURNAL OF NUCLEAR MATERIALS,515,326-337. |
MLA | Ning, Fangqiang,et al."Crevice corrosion behavior of Alloy 690 in high-temperature water".JOURNAL OF NUCLEAR MATERIALS 515(2019):326-337. |
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