Hf. Rea et al., RECOVERY OF TRITIUM OBTAINED AS A BY-PRODUCT IN THE PRODUCTION OF F-18, Journal of radioanalytical and nuclear chemistry, 173(2), 1993, pp. 249-259
For samples of irradiated natural and enriched (95%) Li2CO3, normal di
stillation to dryness of the alumina column eluates permits recuperati
on of approximately 80% of the tritium. The distilled samples were con
centrated by electrolysis and a subsequent vacuum distillation resulte
d in a tritium enrichment of the order of 30%. The enriched samples we
re used to prepare sealed, calibrated sources, with different levels o
f tritium radioactivity, to be used as standards for the determination
of tritium in unknown samples using liquid scintillation.