2024 Annual Meeting

Presentation information

Oral presentation

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

[1G15-17] Hydrogen Isotope Retention for Tungsten

Tue. Mar 26, 2024 4:40 PM - 5:30 PM Room G (21Bildg.3F 21-317)

Chair:Suguru Masuzaki(NIFS)

4:55 PM - 5:10 PM

[1G16] Effect of irradiation damage on hydrogen isotope retention behavior for tungsten-tantalum alloy

*Shingo Okumura1, Kaiji Yamamura2, Hao Yu2, Akira Hasegawa2, Ryuta Kasada2, Yasuhisa Oya1 (1. Shizuoka Univ., 2. Tohoku Univ.)

Keywords:Tungsten-Tantalum, hydrogen isotope behavior

For the operation of fusion reactor, it is necessary to consider the irradiation effects by energetic particles such as deuterium (D), tritium (T), and neutrons, as well as the resistance to high heat loads on Tungsten(W) for plasma-facing materials. In this study, powder metallurgical processed polycrystalline Tungsten-1,3,5% Tantalum(W-1,3,5%Ta) samples were used, which have superior recrystallization behavior and strength. The irradiation defects were introduced by 6 MeV Fe2+ irradiation and 3 keV deuterium ion irradiation was performed to evaluate the deuterium retention behavior by TDS measurement. For the undamaged W-Ta sample, the deuterium retention was increased as increasing Ta concentration compared to that for W, which would be controlled by hydrogen affinity with Ta.

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