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논문 기본 정보

자료유형
학술저널
저자정보
Yao Gang (School of Materials Science and Engineering, Hefei University of Technology) Chen Hong-Yu (College of Mechanical Engineering, Zhejiang University of Technology, Hangzhou) Luo Lai-Ma (School of Materials Science and Engineering, Hefei University of Technology) Zan Xiang (School of Materials Science and Engineering, Hefei University of Technology) Wu Yu-Cheng (School of Materials Science and Engineering, Hefei University of Technology)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology Vol.56 No.6
발행연도
2024.6
수록면
2,141 - 2,152 (12page)
DOI
10.1016/j.net.2024.01.022

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초록· 키워드

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Tungsten is the most promising plasma facing material for fusion reactors. Rolled W–Y2(Zr)O3 bulk material has been successfully produced in this study for future fusion engineering applications. The introduction of Zr is conducive to the refinement of the second phase particles. Nano-sized Y–Zr–O particles are observed in the powder and bulk samples. Related results show that the Y–Zr–O particle dispersion distribution improves the heat load resistance of W–Y2(Zr)O3 composite material. For four-point bend experiments in the same sampling direction, the DBTT of W–Y2(Zr)O3 composite materials is lower compared to the pure tungsten. For the same material, the DBTT of the material was selected for testing along the RD direction is lower compared to the material was selected for testing along the TD direction. Findings of this study provide suggestions for the subsequent industrial preparation of nanoscale particle-doped tungsten materials

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