N. Roux et al., CURRENT MATERIAL AND DESIGN STUDIES FOR THE UTILIZATION OF LI2ZRO3 INTHE BIT BLANKET CONCEPT, Journal of nuclear materials, 215, 1994, pp. 862-867
The DEMO-relevant, helium-cooled, BIT blanket concept jointly develope
d by CEA and ENEA has been originally designed on the basis of LiAlO2
properties data. Owing to its excellent tritium release behaviour Li2Z
rO3 is being evaluated too. Thus, development of the Li2ZrO3 ceramic i
s in progress at CEA and conceptual work is partly devoted to the adap
tation of the design using Li2ZrO3 characteristics. The material devel
opment work is focused on improving the thermomechanical behaviour of
Li2ZrO3 with the aim to ensure ceramic pellet integrity during blanket
operation. Such an improvement should be achieved without significant
change of the tritium release characteristics. Among means being atte
mpted is microstructural tailoring, i.e. density adjustment. Mechanica
l tests, thermal cycling tests and tritium release annealing tests all
ow to evidence any changes. A feasibility study of large scale product
ion of BIT-type Li2ZrO3 pellets was undertaken with industry. In paral
lel, conceptual work is concentrated on redesigning the BIT concept wi
th Li2ZrO3 properties data, on calculation of tritium breeding ratio,
and on evaluation of the maximum lithium burnup in the breeder.