The model to describe tritium release behavior from solid breeder materials has been developed by the blanket group of Kyushu University. It has been found in the course of this experiment that water is released from the solid breeder materials to the purge gas and that this water affects the tritium release behavior. The amount of adsorbed water and the capacity of water formation reaction of Li2TiO3 pebbles are quantified in this study, where Li2TiO3 pebbles considered to use in the test blanket module at ITER by JAEA is experimented. The tritium release behavior from Li2TiO3 blanket is also estimated for the commercial reactor condition or the ITER burning condition. Moreover, the effects of grain size and temperature on the tritium inventory in Li2TiO3 blanket under the steady state condition are evaluated and the optimal grain size is discussed.
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Materials Science(all)
- Nuclear Energy and Engineering