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Irradiation behaviors of two novel single-phase bcc-structure high-entropy alloys for accident-tolerant fuel cladding
Zhang, Zijian1,2; Han, En-Hou1; Xiang, Chao1,3
Corresponding AuthorHan, En-Hou(ehhan@imr.ac.cn)
2021-09-10
Source PublicationJOURNAL OF MATERIALS SCIENCE & TECHNOLOGY
ISSN1005-0302
Volume84Pages:230-238
AbstractHigh-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.
KeywordHigh-entropy alloy Accident-tolerant fuel cladding Helium-ion irradiation Microstructure Irradiation hardening
Funding OrganizationKey Program of the Chinese Academy of Sciences
DOI10.1016/j.jmst.2020.12.058
Indexed BySCI
Language英语
Funding ProjectKey Program of the Chinese Academy of Sciences[ZDRW-CN-2017-1]
WOS Research AreaMaterials Science ; Metallurgy & Metallurgical Engineering
WOS SubjectMaterials Science, Multidisciplinary ; Metallurgy & Metallurgical Engineering
WOS IDWOS:000665531000025
PublisherJOURNAL MATER SCI TECHNOL
Citation statistics
Cited Times:3[WOS]   [WOS Record]     [Related Records in WOS]
Document Type期刊论文
Identifierhttp://ir.imr.ac.cn/handle/321006/160137
Collection中国科学院金属研究所
Corresponding AuthorHan, En-Hou
Affiliation1.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
Recommended Citation
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.
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