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        Xu Qiu: Effects of Zr/Mo in W-Y2O3 Alloys on Plasma Exposure Damage

        發(fā)布時間:2025-09-29
        點擊:
        來源:材料科學與工程學院

        報告時間2025年10月13日(星期一)10:00

        報告地點材料樓601會議室

        報 告 人Xu Qiu  associate professor

        工作單位Kyoto University

        舉辦單位材料科學與工程學院

        報告簡介

        In the present study, we developed Mo- and Zr-added W-Y2O3 composites, and investigated their surface damage, including commercially available W induced by He and D as well as He and D mixture plasmas. Blistering was not observed in the D-plasma-irradiated W and W composites. The thickness of the damaged surface layer due to He plasma exposure of the W-Mo-Y2O3 composite was similar to that of W. However, the thickness of the damaged surface layer of the W-Y2O3 composite was half that of W. In addition, the thickness of the damaged surface layer of the W-Zr-Y2O3 composite was further improved by 5 times. Y2O3 nanoparticles, especially refined Zr-Y-O nanoparticles, act as He trap sites to suppress the formation and growth of He bubbles. Furthermore, the W-O-Y and W-O-Zr-Y nanoparticles increased the solubility of He and delayed He diffusion, hindering the formation of He bubbles.

        報告人簡介

        Xu Qiu, associate professor at the Institute for Integrated Radiation and Nuclear Science, Kyoto University. He graduated from Kyushu University in Japan with a doctorate in engineering in 1995. Then, he joined the Kyoto University Research Reactor Institute as an assistant professor. He has long been engaged in basic research on the interaction of materials with high energy particles (neutrons, ions, electrons). He published more than 290 articles in Scientific Reports, Nanotechnology, Nuclear Fusion, Phys. Rev. B., Phys. Rev. C., Appl. Phys. Lett., Phil. Mag. Lett., Acta Mater., J. Alloy Com., and Journal of Nuclear Materials, and so on. He is an editorial board members of Scientific Reports.


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