Estimation of tritium release behavior from solid breeder materials under the condition of ITER test blanket module

A tritium release model from solid breeder materials has been developed. Tritium release curves estimated using this model gave good agreement with tritium release curves from various solid breeder materials obtained by out-pile experiments under various purge gas conditions in previous study. In this study, tritium release behavior from Li2TiO3 and LiAlO2 are estimated for the neutron irradiation condition and operation sequence of the ITER test blanket module test program (neutron wall loading of 0.78 MW/m2 and repetition of burn time for 400 s with a dwell time of 1400 s). The results are evaluated to discuss the tritium release and inventory performance of different breeder materials.