2022 Annual Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[2L01-04] Plasma-material Interaction in Fusion Reactors

Thu. Mar 17, 2022 9:45 AM - 11:00 AM Room L

Chair: Takuya Nagasaka (NIFS)

9:45 AM - 10:00 AM

[2L01] Evaluation of hydrogen isotope retention behavior and impurities deposition for plasma exposed tungsten samples in QUEST

*Shiori Hirata1, Kyousuke Ashizawa1, Kazuaki Hanada2, Naoki Yoshida2, Yasuhisa Oya1 (1. Shizuoka University, 2. Kyusyu University)

Keywords:tungsten, QUEST, hydrogen isotope behavior

It is essential for the realization of a fusion reactor to evaluate hydrogen isotope behavior. In this study, tungsten samples were exposed to hydrogen plasma during the QUEST 2020S/S and 2021S/S campaigns. The maximum wall temperature of QUEST 2020S/S and 2021S/S campaign were 473 K and 673 K, respectively. These samples surface was observed by transmission electron microscopy and scanning electron microscopy, and their chemical states and hydrogen retention were evaluated by X-ray photoelectron spectroscopy and thermal desorption spectroscopy. The effects of wall temperatures on impurities deposition and hydrogen isotope retention will be presented.