An Investigation on Thermal Desorption Behavior of Deuterium in Beryllium for ITER Tritium Removal System

Intermediate level and long lived radioactive waste (type B radwaste), will be generated from the vacuum vessel of ITER Tokamak building when its structural components are replaced for maintenance. Because nuclear fusion reactor uses deuterium-tritium fuel, plasma facing materials include some tritium on its inside. ITER is considering tritium removal system (TRS), which eliminates tritium in type B radwaste by heating. In the present study, the thermal desorption behavior of hydrogen isotope in Beryllium (Be) was investigated to determine the condition of TRS. TDS analysis was performed in Be at 120, 240 and 350 .deg. C. D₂ concentration and the desorption peak temperature increased with increasing loading temperature. Using peak shift method with three ramp rates of 0.166, 0.332, and 0.5 .deg. C/sec, trap activation energy of D in Be loaded at 350 .deg. C was 67 kJ/mol.