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

The possibility of reprocessing of irradiated [ 18 O]H 2 O after isolation of [ 18 F]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 [ 18 O]H 2 O and the degree of its enrichment in 18 O before and after distillation at atmospheric pressure were studied comprehensively. The suggested method allows efficient removal of long-lived γ-emitting radionuclides ( 56 Co, 57 Co, 58 Co, 65 Zn, 54 Mn, 51 Cr) from the [ 18 O]H 2 O regenerate. The distillation reduces the content of residual solvents (acetaldehyde, acetone, isopropanol, ethanol, acetonitrile), whereas the content of 3H and 18 O in [ 18 O]H 2 O 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.