Presentation Information

3:30 PM - 3:45 PM JST(6:30 AM - 6:45 AM UTC)

[2I11]Effect of Deuterium Plasma Irradiation Temperature on Deuterium Retention Behavior in damaged W-Mo Alloy

*Ayumu Hayakawa¹, Yuzuka Hoshino¹, Shingo Okumura¹, Takeshi Toyama², Akira Hasegawa³, Suguru Masuzaki⁴, Yasuhisa Oya¹ (1. Shizuoka Univ., 2. JAEA, 3. Tohoku Univ., 4. NIFS)

Keywords:

W-Mo,Deuterium plasma,Hydrogen isotope behavior,Irradiation defects,Plasma facing materials

Tungsten (W) is a promising candidate for plasma-facing materials in fusion reactors due to high melting point, low spattering yield and low hydrogen solubility. The introduction of irradiation defects changed the hydrogen isotope trapping behavior in W. The previous report showed that the addition of molybdenum (Mo) to W has induced the resistance of radiation effects. In this study, deuterium plasma exposure was performed at 475 and 573 K, and the effect of irradiation temperature on deuterium retention behavior was studied by TDS. For the undamaged W-Mo alloy, deuterium retention was found to be decreased by the addition of Mo at the plasma irradiation temperature of 473 K.

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