Research progress on zirconium alloys: applications, development trend, and degradation mechanism in nuclear environment

doi:10.1515/corrrev-2024-0075

IMR OpenIR

	Research progress on zirconium alloys: applications, development trend, and degradation mechanism in nuclear environment
	Okonkwo, Bright O.1; Li, Zimin 1; Li, Li 1; Wang, Jianqiu 1,2; Han, En-Hou 1,3
通讯作者	Okonkwo, Bright O.(boo@icost.ac.cn)
	2024-12-25
发表期刊	CORROSION REVIEWS
ISSN	0334-6005
页码	20
摘要	In this paper, the research progress of zirconium (Zr) alloys is critically reviewed from the aspects of application, development status, and degradation mechanism in a nuclear environment. The review focused on the application of Zr alloys in the nuclear industry, which are widely used due to their low thermal neutron absorption, good corrosion resistance, and excellent mechanical properties. However, with the increasing requirements in the chemical and medical fields, the application of Zr alloys in these non-nuclear fields is growing due to their excellent properties like good corrosion resistance and low thermal expansion coefficient, as summarized in this review. Additionally, the degradation mechanisms of Zr alloy exposed to a corrosive environment, i.e., corrosion and hydrogen uptake, and the role of alloying selection in minimizing these two phenomena is considered in this review, based on pretransition kinetics and the loss of oxide protectiveness at transition. This is corroborated by the discussion on alloying elements with beneficial and detrimental effects on the corrosion performance of Zr alloys, as well as elements with contradicting effects on Zr alloys corrosion performance owing to the discrepancies in literature. Overall, this review can be leveraged in future alloy design to further improve Zr alloys corrosion resistance in nuclear applications, thus ultimately improving their integrity.
关键词	corrosion zirconium alloy hydrogen uptake nuclear application
DOI	10.1515/corrrev-2024-0075
收录类别	SCI
语种	英语
WOS研究方向	Electrochemistry ; Metallurgy & Metallurgical Engineering ; Materials Science
WOS类目	Electrochemistry ; Metallurgy & Metallurgical Engineering ; Materials Science, Coatings & Films
WOS记录号	WOS:001382287600001
出版者	WALTER DE GRUYTER GMBH
引用统计	被引频次：1[WOS] [WOS记录] [WOS相关记录]
文献类型	期刊论文
条目标识符	http://ir.imr.ac.cn/handle/321006/181163
专题	中国科学院金属研究所
通讯作者	Okonkwo, Bright O.
作者单位	1.Inst Corros Sci & Technol, Guangzhou 510530, Peoples R China 2.Chinese Acad Sci, CAS Key Lab Nucl Mat & Safety Assessment, Inst Met Res, Shenyang 110016, Peoples R China 3.South China Univ Technol, Sch Mat Sci & Engn, Guangzhou 510006, Peoples R China
推荐引用方式 GB/T 7714	Okonkwo, Bright O.,Li, Zimin,Li, Li,et al. Research progress on zirconium alloys: applications, development trend, and degradation mechanism in nuclear environment[J]. CORROSION REVIEWS,2024:20.
APA	Okonkwo, Bright O.,Li, Zimin,Li, Li,Wang, Jianqiu,&Han, En-Hou.(2024).Research progress on zirconium alloys: applications, development trend, and degradation mechanism in nuclear environment.CORROSION REVIEWS,20.
MLA	Okonkwo, Bright O.,et al."Research progress on zirconium alloys: applications, development trend, and degradation mechanism in nuclear environment".CORROSION REVIEWS (2024):20.