A facility was reconstructed for producing tritium in 40 TBq per batch. Gaseous tritium was extracted from neutron-irradiated 6Li-Al alloy targets by heating at 700°C under vacuum and collected in uranium. The recovery yield of tritium was about 100% and the isotopic purity of the product was about 95%. Through the production run, no leakage of tritium from the facility was observed.
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Tanase et al. (1988) studied this question.
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