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

Abstract

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.