Irradiation behaviors of two novel single-phase bcc-structure high-entropy alloys for accident-tolerant fuel cladding

doi:10.1016/j.jmst.2020.12.058

IMR OpenIR

	Irradiation behaviors of two novel single-phase bcc-structure high-entropy alloys for accident-tolerant fuel cladding
	Zhang, Zijian 1,2; Han, En-Hou 1; Xiang, Chao 1,3
通讯作者	Han, En-Hou(ehhan@imr.ac.cn)
	2021-09-10
发表期刊	JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY
ISSN	1005-0302
卷号	84 页码:230-238
摘要	High-entropy alloys (HEAs) are potential alternative materials for accident-tolerant fuel cladding due to their excellent irradiation resistance and high-temperature corrosion resistance. In this work, two novel body-centered cubic (bcc) structured Mo0.5NbTiVCr0.25 and Mo-0.5 NbTiV0.5 Zr-0.25 HEAs were fabricated. Helium-ion irradiation was performed on the two HEAs to simulate neutron irradiation, and the crystal structure, hardness, and microstructure evolution were investigated. The crystal structure of the Mo0.5NbTiVCr0.25 HEA remained stable at low fluences, while amorphization may occur at high fluences in the two HEAs. The irradiation hardening value of the Mo0.5NbTiVCr0.25 was 0.77 GPa at fluences of 1 x 10(17) ions/cm(2) and 1.49 GPa at fluences of 5 x 10(17) ions/cm(2), while the hardening value of the Mo0.5NbTiVCr0.25Zr0.25 was 1.36 GPa at ion fluences of 5 x 10(17) ions/cm(2). In comparison with most of the conventional alloys, the two HEAs showed slight irradiation hardening. The helium bubbles and dislocation loops with small size were observed in the two HEAs after irradiation. This is the first time to report the formation of a dislocation loop in bcc-structure HEAs after irradiation. However, voids and precipitates were not observed in the two HEAs which could be ascribed to the high lattice distortion and compositional complexity of HEAs. This research revealed that the two HEAs show outstanding irradiation resistance, which may be promising accident-tolerant fuel cladding materials. (C) 2021 Published by Elsevier Ltd on behalf of The editorial office of Journal of Materials Science & Technology.
关键词	High-entropy alloy Accident-tolerant fuel cladding Helium-ion irradiation Microstructure Irradiation hardening
资助者	Key Program of the Chinese Academy of Sciences
DOI	10.1016/j.jmst.2020.12.058
收录类别	SCI
语种	英语
资助项目	Key Program of the Chinese Academy of Sciences[ZDRW-CN-2017-1]
WOS研究方向	Materials Science ; Metallurgy & Metallurgical Engineering
WOS类目	Materials Science, Multidisciplinary ; Metallurgy & Metallurgical Engineering
WOS记录号	WOS:000665531000025
出版者	JOURNAL MATER SCI TECHNOL
引用统计	被引频次：48[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/321006/160137
专题	中国科学院金属研究所
通讯作者	Han, En-Hou
作者单位	1.Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China 2.Univ Sci & Technol China, Sch Mat Sci & Engn, Shenyang 110016, Peoples R China 3.Northeastern Univ, Sch Mat Sci & Engn, Shenyang 110819, Peoples R China
推荐引用方式 GB/T 7714	Zhang, Zijian,Han, En-Hou,Xiang, Chao. Irradiation behaviors of two novel single-phase bcc-structure high-entropy alloys for accident-tolerant fuel cladding[J]. JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY,2021,84:230-238.
APA	Zhang, Zijian,Han, En-Hou,&Xiang, Chao.(2021).Irradiation behaviors of two novel single-phase bcc-structure high-entropy alloys for accident-tolerant fuel cladding.JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY,84,230-238.
MLA	Zhang, Zijian,et al."Irradiation behaviors of two novel single-phase bcc-structure high-entropy alloys for accident-tolerant fuel cladding".JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY 84(2021):230-238.