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Production of no carrier-added (NCA)  199 Au through  nat Pt( n ,  γ ) reaction and subsequent purification using liquid-liquid extraction from other radioisotopes is studied in the context of theranostic application. Comparative separation of NCA  199 Au after dissolution of activated Pt target using three Cyanex compounds (Cyanex-272, Cyanex-302 and Cyanex-923) is evaluated. The extraction process is optimized in terms of the type of extractant, the concentration of extractant, extraction time and aqueous media (HNO 3 , NH 4 OH). Among these extractants, the Cynaex-923 is efficient and promising for rapid separation and production of NCA  199 Au from HNO 3  by high extraction %. Selective extraction of  199 Au from other Pt and Ir radioisotopes is observed. High recovery of  199 Au was obtained in the case of Cyanex-923 using 0.05 M thiourea dissolved in HCl or 2 M NaOH. Our results find the Cyanex-923 as a promising extractant for efficient separation of  199 Au from irradiated Pt target with high yield (99%).

Efficient trace-scale extraction method of reactor produced 199 Au adequate for nuclear medicine applications