Irradiation Behavior in High Entropy Alloys
As an increasing demand of advanced nuclear fission reactors and fusion facilities, the key requirements for the materials used in advanced nuclear systems should encompass superior high temperature property, good behavior in corrosive environment, and high irradiation resistance, etc. Recently, it...
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| Published in | Journal of iron and steel research, international Vol. 22; no. 10; pp. 879 - 884 |
|---|---|
| Main Authors | , , , |
| Format | Journal Article |
| Language | English |
| Published |
Singapore
Elsevier Ltd
01.10.2015
Springer Singapore |
| Subjects | |
| Online Access | Get full text |
| ISSN | 1006-706X 2210-3988 |
| DOI | 10.1016/S1006-706X(15)30084-4 |
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| Abstract | As an increasing demand of advanced nuclear fission reactors and fusion facilities, the key requirements for the materials used in advanced nuclear systems should encompass superior high temperature property, good behavior in corrosive environment, and high irradiation resistance, etc. Recently, it was found that some selected high entropy alloys (HEAs) possess excellent mechanical properties at high temperature, high corrosion resistance, and no grain coarsening and self-healing ability under irradiation, especially, the exceptional structural stability and lower irradiation-induced volume swelling, compared with other conventional materials. Thus, HEAs have been considered as the potential nuclear materials used for future fission or fusion reactors, which are designed to operate at higher temperatures and higher radiation doses up to several hundreds of displacement per atom (dpa). An insight into the irradiation behavior of HEAs was given, including fundamental researches to investigate the irradiation-induced phase crystal structure change and volume swelling in HEAs. In summary, a brief overview of the irradiation behavior in HEAs was made and the irradiation-induced structural change in HEAs may be relatively insensitive because of their special structures. |
|---|---|
| AbstractList | As an increasing demand of advanced nuclear fission reactors and fusion facilities, the key requirements for the materials used in advanced nuclear systems should encompass superior high temperature property, good behavior in corrosive environment, and high irradiation resistance, etc. Recently, it was found that some selected high entropy alloys （HEAs） possess excellent mechanical properties at high temperature, high corrosion resistance, and no grain coarsening and self-healing abil- ity under irradiation, especially, the exceptional structural stability and lower irradiation-induced volume swelling, compared with other conventional materials. Thus, HEAs have been considered as the potential nuclear materials used for future fission or fusion reactors, which are designed to operate at higher temperatures and higher radiation doses up to several hundreds of displacement per atom （dpa）. An insight into the irradiation behavior of HEAs was given, including fundamental researches to investigate the irradiation-induced phase crystal structure change and volume swelling in HEAs. In summary, a brief overview of the irradiation behavior in HEAs was made and the irradiation-induced structural change in HEAs may be relatively insensi- tive because of their special structures. As an increasing demand of advanced nuclear fission reactors and fusion facilities, the key requirements for the materials used in advanced nuclear systems should encompass superior high temperature property, good behavior in corrosive environment, and high irradiation resistance, etc. Recently, it was found that some selected high entropy alloys (HEAs) possess excellent mechanical properties at high temperature, high corrosion resistance, and no grain coarsening and self-healing ability under irradiation, especially, the exceptional structural stability and lower irradiation-induced volume swelling, compared with other conventional materials. Thus, HEAs have been considered as the potential nuclear materials used for future fission or fusion reactors, which are designed to operate at higher temperatures and higher radiation doses up to several hundreds of displacement per atom (dpa). An insight into the irradiation behavior of HEAs was given, including fundamental researches to investigate the irradiation-induced phase crystal structure change and volume swelling in HEAs. In summary, a brief overview of the irradiation behavior in HEAs was made and the irradiation-induced structural change in HEAs may be relatively insensitive because of their special structures. |
| Author | Song-qin XIA Zhen WANG Teng-fei YANG Yong ZHANG |
| AuthorAffiliation | State Key Laboratory for Advanced Metals and Materials, University of Science and Technology Beijing, Beijing 100083, China Institute for Science and Technology Information and Strategy, Central Iron and Steel Research Institute, Beijing 100081, China State Key Laboratory of Nuclear Physics and Technology, Center for Applied Physics and Technology, Peking University, Beijing 100871, China |
| Author_xml | – sequence: 1 givenname: Song-qin surname: XIA fullname: XIA, Song-qin email: xsq2417@163.com organization: State Key Laboratory for Advanced Metals and Materials, University of Science and Technology Beijing, Beijing 100083, China – sequence: 2 givenname: Zhen surname: WANG fullname: WANG, Zhen organization: Institute for Science and Technology Information and Strategy, Central Iron and Steel Research Institute, Beijing 100081, China – sequence: 3 givenname: Teng-fei surname: YANG fullname: YANG, Teng-fei organization: State Key Laboratory of Nuclear Physics and Technology, Center for Applied Physics and Technology, Peking University, Beijing 100871, China – sequence: 4 givenname: Yong surname: ZHANG fullname: ZHANG, Yong email: drzhangy@ustb.edu.cn organization: State Key Laboratory for Advanced Metals and Materials, University of Science and Technology Beijing, Beijing 100083, China |
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| Notes | As an increasing demand of advanced nuclear fission reactors and fusion facilities, the key requirements for the materials used in advanced nuclear systems should encompass superior high temperature property, good behavior in corrosive environment, and high irradiation resistance, etc. Recently, it was found that some selected high entropy alloys （HEAs） possess excellent mechanical properties at high temperature, high corrosion resistance, and no grain coarsening and self-healing abil- ity under irradiation, especially, the exceptional structural stability and lower irradiation-induced volume swelling, compared with other conventional materials. Thus, HEAs have been considered as the potential nuclear materials used for future fission or fusion reactors, which are designed to operate at higher temperatures and higher radiation doses up to several hundreds of displacement per atom （dpa）. An insight into the irradiation behavior of HEAs was given, including fundamental researches to investigate the irradiation-induced phase crystal structure change and volume swelling in HEAs. In summary, a brief overview of the irradiation behavior in HEAs was made and the irradiation-induced structural change in HEAs may be relatively insensi- tive because of their special structures. 11-3678/TF high entropy alloy; irradiation behavior; self-healing; structure change; volume swelling |
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| SubjectTerms | Applied and Technical Physics Engineering high entropy alloy irradiation behavior Machines Manufacturing Materials Engineering Materials Science Metallic Materials Physical Chemistry Processes Review self-healing structure change volume swelling 体积膨胀 先进核能系统 合金 核聚变反应堆 熵 结构稳定性 辐照行为 高温力学性能 |
| Title | Irradiation Behavior in High Entropy Alloys |
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