Tritium traps in neutron irradiated ceramics from out-of-pile constant rate heating measurements (EEC program)

Constant rate heating experiments have been performed in order to compare tritium release of pre-irradiated lithium ceramics. Samples of sintered aluminates modified by replacement of 1.6% of the lithiumby magnesium exhibits a tritium release at Lower temperature; the profile of concentration of tritium often exhibits several peaks and shoulders, proving various kinds of tritium trapping. Many pre-irradiation examinations of the samples were pursued and seem to show electrical defects. Our first results seem promising both for the understanding of the gas release mecanism, and for the possible modification of caracteristics of retention-release of an important fraction of the generated gases, induced by doping the ceramic. (author). 3 refs.; 11 figs