Measurements of tritium and helium in fast neutron irradiated lithium ceramics using high temperature vacuum extraction

Tritium and helium retention measurements have been performed at the Hanford Engineering Development Laboratory on fast neutron irradiated lithium ceramic materials from solid breeder closed capsule test FUBR-1A. The lithium ceramic materials discussed at this time include Li2O, LiAlO2, and Li2ZrO3. The experimental conditions forming the test matrix include 6Li burnup levels of 1, 2, and 3%, and irradiation temperatures of 7730, 9730 and 11730K, for the three materials. Included will be a discussion of mechanisms controlling tritium retention. The retention measurements reported here were obtained using a rapid, high temperature vacuum extraction method, utilizing newly designed apparatus. This new apparatus will be described, along with developmental supporting data