Research Progress of Tungsten-Based Plasma Materials in Fusion Reactors

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作者
Zhao, Yiluo [1 ]
Lei, Ming [1 ]
Zhang, Xu [1 ]
Feng, Yong [2 ]
Zhao, Yong [1 ,3 ]
机构
[1] Key Laboratory of Advanced Technology of Materials, Superconductivity and New Energy R&D Center, Southwest Jiaotong University, Chengdu,610031, China
[2] Western Superconducting Materials Technology Co., Ltd, Xi'an,710018, China
[3] College of Physics and Energy, Fuzhou Normal University, Fuzhou,350117, China
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摘要
Tungsten-based materials with high melting point, high thermal conductivity, low vapor pressure and low tritium retention have become plasma oriented materials with broad application prospects. Due to its shortcomings in low temperature brittleness, recrystallization brittleness and irradiation damage, its application in engineering is limited, and it has become a research hotspot in the field of nuclear fusion materials. In this paper, the research status of tungsten-oriented plasma-oriented materials was reviewed, the damage caused by four kinds of particle irradiation and four kinds of commonly used methods to improve the properties of tungsten materials were described, and the problems that need to be solved were also discussed. © 2021, Science Press. All right reserved.
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页码:3399 / 3407
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