H. Kwast et al., THE BEHAVIOR OF CERAMIC BREEDER MATERIALS WITH RESPECT TO TRITIUM RELEASE AND PELLET PEBBLE MECHANICAL INTEGRITY/, Journal of nuclear materials, 215, 1994, pp. 1010-1014
In situ tritium release experiments from several candidate fusion blan
ket ceramic breeder materials have been performed in the High Flux Rea
ctor (HFR) at Petten over the last few years. The sixth experiment, EX
OTIC-6, contained pellets of LiAlO2, Li2ZrO3, Li6Zr2O7 and Li8ZrO6 and
pebbles of Li4SiO4 and Li2ZrO3 which were irradiated up to a lithium
burnup of 3%. A large number of temperature transients and purge gas c
omposition changes were performed. From the temperature transients tri
tium residence times have been determined. Some preliminary results we
re presented at the 17th Symposium on Fusion Technology (SOFT) held in
Rome in 1992. In the present paper results of a further analysis of t
he residence times are presented together with some postirradiation ex
amination results. The LiAlO2 pellets showed a better mechanical stabi
lity than the Li-zirconates pellets. The pebbles remained intact. The
tritium residence times determined from the tritium inventories were i
n good agreement with those previously determined from temperature tra
nsients. The tritium release characteristics of the materials investig
ated remain substantially unchanged up to the maximum lithium burnup a
chieved in this experiment.