[2L01-05] Engineering of Plasma Facing Components

[2L05] Tritium retention behaviour for tungsten and tungsten-10%rhenium

*Yuki Koyama¹, Kyosuke Ashizawa¹, Shiori Hirata¹, Naoko Ashikawa^2,3, Yoji Someya⁴, Yuji Hatano⁵, Yasuhisa Oya¹ (1. Shizuoka Univ., 2. NIFS, 3. SOKENDAI, 4. QST, 5. Univ. of Toyama)

Keywords:Tungsten-rhenium alloy, Tritium, Tritium retention behavior, Imaging plate, β-ray-Induced X-ray Spectrometry, Thermal desorption spectroscopy

In the fusion reactor, tungsten (W) as a first wall material is transmuted into rhenium (Re) by nuclear reaction. For evaluation of hydrogen isotope, material parameter of W-Re alloy related to hydrogen isotope transport is crucial. In this study, un-damaged W, deuterium (D) plasma irradiated W, Fe ion irradiated W and D plasma-Fe ion irradiated W were exposed Tritium (T) gas or implanted T ion, and W-10%Re was exposed T gas. Thereafter Imaging plate, β-ray-Induced X-ray Spectrometry (BIXS) and Thermal desorption spectroscopy for the above samples were performed. BIXS result indicated that D reduce T concentration in the bulk.