Current development of body-centered cubic high-entropy alloys for nuclear applications

被引:0
|
作者
Tan Shi [1 ]
Peng-Hui Lei [1 ]
Xu Yan [1 ]
Jing Li [1 ]
Yun-Di Zhou [1 ]
Yun-Peng Wang [1 ]
Zheng-Xiong Su [1 ]
Yan-Kun Dou [2 ]
Xin-Fu He [2 ]
Di Yun [1 ]
Wen Yang [2 ]
Chen-Yang Lu [1 ]
机构
[1] Department of Nuclear Science and Technology,Xi’an Jiaotong University
[2] China Institute of Atomic Energy
基金
中国国家自然科学基金;
关键词
Body-centered cubic high-entropy alloys; Refractory high-entropy alloys; Nuclear materials; Radiation damage; Tungsten;
D O I
暂无
中图分类号
TL34 [反应堆材料及其性能]; TG139 [其他特种性质合金];
学科分类号
080502 ; 082701 ;
摘要
High-entropy alloys greatly expand the alloy design range and offer new possibilities for improving material performance. Based on the worldwide research efforts in the last decade, the excellent mechanical properties and promising radiation and corrosion resistance of this group of materials have been demonstrated. High-entropy alloys with body-centered cubic(BCC) structures, especially refractory high-entropy alloys, are considered as promising materials for high-temperature applications in advanced nuclear reactors. However, the extreme reactor conditions including high temperature, high radiation damage, high stress, and complex corrosive environment require a comprehensive evaluation of the material properties for their actual service in nuclear reactors. This review summarizes the current progress on BCC high-entropy alloys from the aspects of neutron economy and activation, mechanical properties, high-temperature stability, radiation resistance, as well as corrosion resistance. Although the current development of BCC high-entropy alloys for nuclear applications is still at an early stage as the large design space of this group of alloys has not been fully explored, the current research findings provide a good basis for the understanding and prediction of material behaviors with different compositions and microstructures. Further in-depth understanding of the degradation mechanisms and characterization of material properties in response to conditions close to reactor environment are necessary. A critical down-selection of potential candidates is also crucial for further comprehensive evaluation and engineering validation.
引用
收藏
页码:197 / 217
页数:21
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