[1G15-17] Hydrogen Isotope Retention for Tungsten

[1G17] Effect of neutron irradiation on formation of irradiation defect and hydrogen isotope retention behavior for W-Re alloy

*Ayumu Hayakawa¹, Yuzuka Hoshino¹, Asahi Sanfukuji¹, Takeshi Toyama², Yasuhisa Oya¹ (1. Shizuoka Univ., 2. Tohoku Univ.)

Keywords:Tungsten-rhenium, Neutron irradiation , Hydrogen isotope behavior

In the fusion reactor, energy is obtained using a fusion reaction of deuterium (D) and tritium (T). Tungsten (W) is a promising candidate for plasma-facing materials in fusion reactors due to its low spattering yield, high melting point, and low hydrogen solubility. During the operation of the fusion reactor, W will be irradiated by high flux D, T and neutron, which will introduce irradiation defects. In addition, W will be transmuted to rhenium (Re) by the nuclear reaction with neutron. PAS and D⁺ irradiation-TDS were performed on neutron damaged W and W-Re. The positron lifetime for undamaged W-Re was shorter than undamaged W. It was considered that Re would reduce the size of intrinsic defects.