摘要

For securing an adequate tritium supply to sustain the D/T fusion reaction, lithium-containing ceramics,such as Li(2)O, LiAlO(2), Li(2)ZrO(3), Li(2)TiO(3), Li(4)SiO(4), are considered strongly as tritium breeding materials for fusion reactor blankets. Lithium ceramic tritium breeders have favorable chemical behavior, good thermomechanical properties and excellent tritium release performance, thereinto their tritium release performance in neutron irradiation is the primary technique target in the test blanket module. Many aspects are sumed up in this paper; properties of the irradiated ceramic tritium breeders ( chemical stability, thermomechanical properties, ion conductivity, neutron activation and so on), tritium release behavior in pile and out of pile, influence factors on tritium diffuse or transfer in ceramic breeders,and correlation between tritium release and annihilation of irradiation defects. In support of the development of Helium Cooled Pebble Bed Test Blanket Module(HCPB TBM), many fundamental research subjects need further study in china. In the future, much efforts should focus on the lithium ceramics' properties at high burnup(>10%) and at high damage rates. In particular, the tritium release behaviour at integrated engineering conditions in the test blanket of ITER, including neutron multiplier, magnetic field, plasma induced current and so on, remains to be known.