Abstract
Gallium-67(67Ga) is usually produced by the irradiation of enriched Zinc-68(68Zn) with protons up to about 28 MeV. It is commercially available as 67Ga chloride and 67Ga citrate(for a recent review of gallium radiopharmaceutical chemistry, see reference one1). At Mount Sinai, 67Ga is routinely produced in quantities of 40–50 Ci per week. One method of processing 67Ga involves the dissolution of the 68Zn and the 67Ga in 7N HC1 and extraction of the 67Ga with isopropyl ether2; our procedure is based on this method. In an on-going effort to improve various aspects of the production process, we have reinvestigated the extraction of 67Ga from targets of 68Zn plated on copper and irradiated with 26.5 MeV protons. The present study was designed to determine the percentage of residual 67Ga on the etching apparatus and the subsequent recovery of this 67Ga(which appears not to be readily removed with acid) using water.
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© 1991 Springer Science+Business Media New York
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Boothe, T.E., Tavano, E., Munoz, J., Carroll, S.T., Smith, P.M. (1991). Improved Extraction Efficiency of Gallium-67 after Irradiation of Zinc-68 with Protons. In: Emran, A.M. (eds) New Trends in Radiopharmaceutical Synthesis, Quality Assurance, and Regulatory Control. Springer, Boston, MA. https://doi.org/10.1007/978-1-4899-0626-7_17
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DOI: https://doi.org/10.1007/978-1-4899-0626-7_17
Publisher Name: Springer, Boston, MA
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