Lithium-based ceramics have long been recognized as promising tritium-
breeding materials for fusion reactor blankets. In particular, their h
igh thermal stability and chemical inertness are favorable safety char
acteristics. The most important qualification for a candidate ceramic
breeder material is most likely, the ability to withstand the rigors o
f long-term irradiation at high temperature and under large temperatur
e gradients. As a group, the lithium-based ceramics have shown good ir
radiation behaviour and excellent tritium release characteristics. Ind
ividual materials performance will depend upon the actual application,
namely, pebble bed versus pellet concept, higher versus lower cooling
temperature, etc. Recently Li2ZrO3 and Li2TiO3 were selected as the b
reeder material for the ITER breeding blanket due to their excellent t
ritium release behaviour at low temperature. Issues being addressed in
support of current blanket design studies will be highlighted. (C) 19
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