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Crevice corrosion behavior of Alloy 690 in high-temperature water
Ning, Fangqiang1,2; Wu, Xinqiang1; Tan, Jibo1
Corresponding AuthorWu, Xinqiang(xqwu@imr.ac.cn)
2019-03-01
Source PublicationJOURNAL OF NUCLEAR MATERIALS
ISSN0022-3115
Volume515Pages:326-337
AbstractCharacterizations 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.
KeywordAlloy Crevice corrosion Oxidation High-temperature corrosion XPS
Funding OrganizationNational 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
DOI10.1016/j.jnucmat.2018.12.050
Indexed BySCI
Language英语
Funding ProjectNational 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 AreaMaterials Science ; Nuclear Science & Technology
WOS SubjectMaterials Science, Multidisciplinary ; Nuclear Science & Technology
WOS IDWOS:000456805800031
PublisherELSEVIER SCIENCE BV
Citation statistics
Cited Times:6[WOS]   [WOS Record]     [Related Records in WOS]
Document Type期刊论文
Identifierhttp://ir.imr.ac.cn/handle/321006/131328
Collection中国科学院金属研究所
Corresponding AuthorWu, Xinqiang
Affiliation1.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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