Reprocessing of Irradiated [18O]H2O under the Conditions of a PET Center


The possibility of reprocessing of irradiated [18O]H2O after isolation of [18F]fluoride ion from it (regenerate) under the conditions of the cyclotron-radiochemical laboratory of an operating PET center was examined. The radionuclide and chemical composition of [18O]H2O and the degree of its enrichment in 18O before and after distillation at atmospheric pressure were studied comprehensively. The suggested method allows efficient removal of long-lived γ-emitting radionuclides (56Co, 57Co, 58Co, 65Zn, 54Mn, 51Cr) from the [18O]H2O regenerate. The distillation reduces the content of residual solvents (acetaldehyde, acetone, isopropanol, ethanol, acetonitrile), whereas the content of 3H and 18O in [18O]H2O changes within the measurement uncertainty. The distillation residues and decontamination solutions after neutralization can be jointly cemented to incorporate the γ-emitters into a compact matrix with the aim of its subsequent delivery to specialized organizations performing long-term storage and disposal of solid radioactive waste.

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Correspondence to S. D. Brinkevich.

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The authors declare that they have no conflict of interest.

Russian Text © The Author(s), 2019, published in Radiokhimiya, 2019, Vol. 61, No. 4, pp. 344–350.

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Brinkevich, S.D., Krot, V.O., Brinkevich, D.I. et al. Reprocessing of Irradiated [18O]H2O under the Conditions of a PET Center. Radiochemistry 61, 483–490 (2019).

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  • [18O]H2O regenerate
  • [18F]fluoride
  • long-lived radionuclides
  • radiopharmaceuticals
  • distillation
  • tritium