Irradiation behaviors of two novel single-phase bcc-structure high-entropy alloys for accident-tolerant fuel cladding
文献类型：期刊论文
| 作者 | Zhang, Zijian1,2; Han, En-Hou1; Xiang, Chao1,3 |
| 刊名 | JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY
 |
| 出版日期 | 2021-09-10 |
| 卷号 | 84页码:230-238 |
| 关键词 | High-entropy alloy Accident-tolerant fuel cladding Helium-ion irradiation Microstructure Irradiation hardening |
| ISSN号 | 1005-0302 |
| DOI | 10.1016/j.jmst.2020.12.058 |
| 通讯作者 | Han, En-Hou(ehhan@imr.ac.cn) |
| 英文摘要 | 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. |
| 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 |
| 语种 | 英语 |
| WOS记录号 | WOS:000665531000025 |
| 出版者 | JOURNAL MATER SCI TECHNOL |
| 资助机构 | Key Program of the Chinese Academy of Sciences |
| 源URL | [http://ir.imr.ac.cn/handle/321006/160136]  |
| 专题 | 金属研究所_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. |
入库方式： OAI收割
来源：金属研究所
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