The 186gRe can be produced in carrier-added (CA) form by (n,y) reaction on enriched 185Re target in thermal nuclear reactor, with a lower specific activity AS than the theoretical carrier-free one (CF). Alternatively, it can be produced by either proton or deuteron irradiation on very highly enriched 186W target in no-carrier-added form (NCA), reaching a AS value very close to the CF one. The attention is focused on 186gRe due to its remarkable applications in for metabolic radiotherapy of tumors. A selective and efficient radiochemical separation of Re radionuclides was set up after irradiation of W metal target of natural isotopic composition. The separation was applied to enriched 186W powdered target too, with similar results. The separation was based on a radiochromatographic step, leading to a quantitative (99%) radiochemical yield for 186gRe and a high decontamination factor from W target, measured by 187W, obtained by 186W(n,y) activation.
Radiochemical separation and quality control of high specific activity Re-186g in no-carrier-added form from cyclotron irradiated W and W-186 targets / M.L. Bonardi, F. Groppi, E. Persico, E. Quartapelle Procopio, A. Gandini, M. Marchetti, S. Manenti - In: NRC7: seventh international conference on nuclear and radiochemistry : 24-29 August 2008, BudapestBudapest : [MKE], 2008 Aug. - ISBN 978-963-9319-80-6. - pp. 150-150 (( Intervento presentato al 7. convegno International conference on nuclear and radiochemistry tenutosi a Budapest, Hungary nel 2008.
Radiochemical separation and quality control of high specific activity Re-186g in no-carrier-added form from cyclotron irradiated W and W-186 targets
M.L. Bonardi;F. Groppi;E. Persico;E. Quartapelle Procopio;S. Manenti
2008
Abstract
The 186gRe can be produced in carrier-added (CA) form by (n,y) reaction on enriched 185Re target in thermal nuclear reactor, with a lower specific activity AS than the theoretical carrier-free one (CF). Alternatively, it can be produced by either proton or deuteron irradiation on very highly enriched 186W target in no-carrier-added form (NCA), reaching a AS value very close to the CF one. The attention is focused on 186gRe due to its remarkable applications in for metabolic radiotherapy of tumors. A selective and efficient radiochemical separation of Re radionuclides was set up after irradiation of W metal target of natural isotopic composition. The separation was applied to enriched 186W powdered target too, with similar results. The separation was based on a radiochromatographic step, leading to a quantitative (99%) radiochemical yield for 186gRe and a high decontamination factor from W target, measured by 187W, obtained by 186W(n,y) activation.
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