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Recovery of tritium obtained as a by-product in the production of fluorine-18

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Abstract

For samples of irradiated natural and enriched (95%) Li2CO3, normal distillation to dryness of the alumina column eluates permits recuperation of approximately 80% of the tritium. The distilled samples were concentrated by electrolysis and a subsequent vacuum distillation resulted in a tritium enrichment of the order of 30%. The enriched samples were used to prepare sealed, calibrated sources, with different levels of tritium radioactivity, to be used as standards for the determination of tritium in unknown samples using liquid scintillation.

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Authors and Affiliations

  1. Instituto Nacional de Investigaciones Nucleares, Col. Escandón, Deleg. M. Hidalgo, Apartado Postal 18-1027, 11801, México, D. F., (Mexico)

    H. F. Rea, F. A. Palma G & F. de M. Ramírez

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  1. H. F. Rea
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  2. F. A. Palma G
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  3. F. de M. Ramírez
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Rea, H.F., Palma G, F.A. & Ramírez, F.d.M. Recovery of tritium obtained as a by-product in the production of fluorine-18. Journal of Radioanalytical and Nuclear Chemistry, Articles 173, 249–259 (1993). https://doi.org/10.1007/BF02043027

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