Preliminary exploration of a WTaVTiCr high-entropy alloy as a plasma-facing material

doi:10.1088/1741-4326/ac8fa5

	Preliminary exploration of a WTaVTiCr high-entropy alloy as a plasma-facing material
	Li, Yu 2,3; Sun, Yuhan 4; Cheng, Long 4; Yuan, Yue 4; Jia, Baohai 5; He, Jiaqing 5; Lu, Guang-Hong 4; Luo, Guang-Nan 1,6; Zhu, Qiang 2,3
刊名	NUCLEAR FUSION
	2022-12-01
卷号	62
关键词	high-entropy alloys plasma-facing materials nuclear fusion
ISSN号	0029-5515
DOI	10.1088/1741-4326/ac8fa5
通讯作者	Zhu, Qiang(zhuq@sustech.edu.cn)
英文摘要	With great power comes great challenges. For nuclear fusion, the holy grail of energy, taming the flame of a miniature star in a solid container remains one of the most fundamental challenges. A tungsten armour for the solid container marks a temporary triumph-a solution adopted by the world's largest fusion experiment, ITER-but may be insufficient for future challenges. High-entropy alloys (HEAs), which are characteristic of a massive compositional space, may bring new solutions. Here, we explore their potential as plasma-facing materials (PFMs) with a prototype W57Ta21V11Ti8Cr3 HEA that was designed by exploiting the natural-mixing tendency among low-activation refractory elements. Revealed by x-ray diffraction analysis and energy-dispersive x-ray spectroscopy, it predominantly consists of a single bcc-phase but with V, Ti, and Cr segregation to grain boundaries and at precipitates. Its yield strength improves similar to 60% at room temperature and oxidation rate reduces similar to 6 times at 1273 K, compared with conventionally used W. The Ti-V-Cr rich segregations and the formed CrTaO4 compound contribute to the improved oxidation resistance. However, the Ti-V-Cr rich segregations, along with the decreasing valence-electron concentration of the matrix by the addition of Ta, V and Ti elements, considerably increase the deuterium retention of the W57Ta21V11Ti8Cr3 HEA to similar to 675 multiples of recrystallized W. Moreover, its thermal conductivity decreases, being similar to 40% of W at 973 K. However, the maximum tolerable steady-state heat load is still similar to 84% of W because of its exceedingly high yield strength at elevated temperatures. Overall, despite being preliminary, we expect HEAs to play an important role in the development of advanced PFMs, for their disadvantages are likely to be compensated by their advantages or be overcome by composition optimization.
资助项目	China Postdoctoral Science Foundation[2022M711468] ; Shenzhen Science and Technology Innovation Commission[JCYJ20210324104610029] ; Shenzhen Science and Technology Innovation Commission[KQTD20170328154443162] ; Shenzhen Science and Technology Innovation Commission[ZDSYS201703031748354]
WOS关键词	TUNGSTEN
WOS研究方向	Physics
语种	英语
出版者	IOP Publishing Ltd
WOS记录号	WOS:000859467400001
资助机构	China Postdoctoral Science Foundation ; Shenzhen Science and Technology Innovation Commission
内容类型	期刊论文
源URL	[http://ir.hfcas.ac.cn:8080/handle/334002/129087]
专题	中国科学院合肥物质科学研究院
通讯作者	Zhu, Qiang
作者单位	1.Univ Sci & Technol China, Hefei 230026, Peoples R China 2.Southern Univ Sci & Technol, Dept Mech & Energy Engn, Shenzhen 518055, Peoples R China 3.Shenzhen Key Lab Addit Mfg High Performance Mat, Shenzhen 518055, Peoples R China 4.Beihang Univ, Sch Phys, Beijing 100191, Peoples R China 5.Southern Univ Sci & Technol, Dept Phys, Shenzhen 518055, Peoples R China 6.Chinese Acad Sci, HFIPS, Inst Plasma Phys, Hefei 230031, Peoples R China
推荐引用方式 GB/T 7714	Li, Yu,Sun, Yuhan,Cheng, Long,et al. Preliminary exploration of a WTaVTiCr high-entropy alloy as a plasma-facing material[J]. NUCLEAR FUSION,2022,62.
APA	Li, Yu.,Sun, Yuhan.,Cheng, Long.,Yuan, Yue.,Jia, Baohai.,...&Zhu, Qiang.(2022).Preliminary exploration of a WTaVTiCr high-entropy alloy as a plasma-facing material.NUCLEAR FUSION,62.
MLA	Li, Yu,et al."Preliminary exploration of a WTaVTiCr high-entropy alloy as a plasma-facing material".NUCLEAR FUSION 62(2022).