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Surface modifications on unirradiated and ion-irradiated tungsten after exposed to deuterium plasma at LHD divertor-leg position

In order to clarify the divertor plasma-induced tungsten (W) surface modifications as well as the irradiation defects effect, two kinds of ITER grade W were exposed to the large helical device deuterium (D) plasma at the divertor-leg position. One was the iron (Fe) ion irradiated W to produce irradi...

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Главные авторы: Mingzhong Zhao, S. Masuzaki, M. Tokitani, M. Yajima, M.I. Kobayashi, K. Yabuuchi, Y. Oya
Формат: Artigo
Язык:Inglês
Опубликовано: IOP Publishing 2025-01-01
Серии:Nuclear Fusion
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Online-ссылка:https://doi.org/10.1088/1741-4326/adb862
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