Neutron irradiation damage for first wall materials in hybrid reactor

Displacement damage and fission gases production due to neutron irradiation damage of the first wall materials W, Fe and Be are analyzed by MC program and irradiation damage program. The results show that hybrid reactor can significantly reduce the requirements on damage of the first wall materials comparing with the pure fusion reactor. Among the materials W, Fe and Be, displacement damage of Be is the minimum for pure fusion reactor and displacement damage and fission gases of W are the minimum for hybrid reactor. From the point of view of neutron irradiation damage, Be is the most suitable for the first wall material of pure fusion reactor, while, W is the most suitable for the first wall material of hybrid reactor among the materials W, Fe and Be.