2023 Fall Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-4 Reactor Component Technology, First Wall, Divertor, Magnet

[3L01-02] Divertor

Fri. Sep 8, 2023 10:00 AM - 10:35 AM Room L (ES Bildg. 3F ES033)

Chair:Shunsuke Kenjo(QST)

10:00 AM - 10:15 AM

[3L01] D retention behavior for damaged W-Re alloy after DPE D+He mixed plasma exposure

*Yasuhisa Oya1, Yuzuka Hoshino1, Tatsuya Hinoki2, Kiyohiro Yabuuchi2, Robert Kolashinski3, Chase N. Taylor4, Masashi Shimada4 (1. Shizuoka Univ., 2. Kyoto Univ., 3. SNL, 4. INL)

Keywords:W-Re alloy, Hydrogen isotope behavior, irradiation defect, D+He mixed plasma exposure

The effect of Re on hydrogen isotope retention should be well understood under high-flux plasma exposure. The Deuterium Plasma Experiment (DPE) device, a high-flux RF-plasma source, has several unique features well-suited for this kind of work. This paper focuses on the comparison of D retention for W and W-Re materials following DPE D+He mixed plasma exposure. Significant D desorption was observed at ~ 900 K and D retention for W-10%Re was higher compared with pure W at 523 K due to lower exposure temperature. The damaged W-10%Re had higher D and He retentions. The D desorption temperature had shifted toward higher temperature side. But, the He desorption temperature was not changed significantly. He trapping site had no large impact by irradiation damage. However, the He retention has largely changed.

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