Crevice corrosion behavior of Alloy 690 in high-temperature water

doi:10.1016/j.jnucmat.2018.12.050

CORC > 金属研究所 > 中国科学院金属研究所

	Crevice corrosion behavior of Alloy 690 in high-temperature water
	Ning, Fangqiang 1,2; Wu, Xinqiang 2; Tan, Jibo 2
刊名	JOURNAL OF NUCLEAR MATERIALS
	2019-03-01
卷号	515 页码:326-337
关键词	Alloy Crevice corrosion Oxidation High-temperature corrosion XPS
ISSN号	0022-3115
DOI	10.1016/j.jnucmat.2018.12.050
通讯作者	Wu, Xinqiang(xqwu@imr.ac.cn)
英文摘要	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.
资助项目	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研究方向	Materials Science ; Nuclear Science & Technology
语种	英语
出版者	ELSEVIER SCIENCE BV
WOS记录号	WOS:000456805800031
资助机构	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
内容类型	期刊论文
源URL	[http://ir.imr.ac.cn/handle/321006/131327]
专题	金属研究所_中国科学院金属研究所
通讯作者	Wu, Xinqiang
作者单位	1.Univ Sci & Technol China, Sch Mat Sci & Engn, Hefei 230026, Anhui, Peoples R China 2.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
推荐引用方式 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.