Abstract
Post-irradiation tritium extraction from γ-LiAlO 2, samples irradiated to 2 × 10 17 n/cm 2 in quartz ampoules produced mostly tritiated water. During in-pile experiments the sample container material influences the ratio of tritium gas to tritiated water. Stainless steel capsules yield more T 2 gas than quartz capsules probably because of a reduction process. Difficulties in interpretation arise from adsorption of tritiated water on the measuring lines. Both experiments showed that much faster extraction rates are obtained from small grain size than large grain size samples at the same open porosity. If diffusion in the grains controls the extraction rates, apparent D values vary from 10 16 to 1.5 × 10 −15 cm 2/s in the temperature range explored. Around 500°C small grain samples reached an equilibrium tritium concentration of a few mCi in 4 h. Such values are suitable for a blanket concept.
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