Abstract
BEATRIX-II is an in situ tritium recovery experiment in the fast flux test facility (FFTF) reactor designed to characterize the feasibility of utilizing solid breeder materials at extended burnups in a fast neutron flux. Although not yet complete, the BEATRIX-II experiments have already substantiated that the solid breeder selected for ITER, Li2O, has good irradiation stability and tritium recovery. Temperature stability, lithium transport, dimensional stability and tritium recovery issues of Li2O up to 5% Li burnup were addressed in this experiment, Temperature gradients far more severe than in the ITER design, 400 to 1000°C, were found to be essentially unchanged by burnup and produced no observable instability, either from swelling or lithium vapor transport. Temperature change experiments illustrated that lithium inventories do not appear to increase as a result of irradiation to burnups of 5%.
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