Design study of tritium breeding blankets for fusion power reactor

The key functions required for tritium breeding blankets for a fusion power reactor are: (1) self-sufficient tritium breeding, (2) in-situ tritium recovery and low tritium inventory, (3) high temperature cooling giving a high efficiency of electricity generation and (4) thermo-mechanical reliability and simplified remote maintenance to obtain high plant availability. Blanket performance is substantially governed by materials selection. Major options of structure/breeder/coolant/neutron multiplier materials considered here are PCA/Li2O/H2O/Be, Mo-alloy/Li2O/He/Be, Mo-alloy/LiAlO2/He/Be, V-alloy/Li/Li/none, and Mo-alloy/Li/He/none. In this report, major blanket characteristics are discussed based on the results obtained from individual design studies which have included remote maintenance of blankets, tritium recovery system, heat transport and energy conversion systems. In addition, technological problems and critical R and D issues for power reactor blanket development are also identified. (author)