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

Author:

Attallah Mohamed F.1,Shahr El-Din Ahmed M.1,Gizawy Mohamed A.2,Ali Amal M. I.3

Affiliation:

1. Analytical Chemistry and Control Department , Hot Laboratories Center, Atomic Energy Authority of Egypt , P.O. Box 13759 , Cairo , Egypt

2. Radioisotopes Production Facility (RPF), Atomic Energy Authority of Egypt , P.O. Box 13759 , Cairo , Egypt

3. Technology of Nuclear Fuel Department , Hot Laboratories Center, Atomic Energy Authority of Egypt , 13759 Abu Zaabal , Cairo , Egypt

Abstract

Abstract Production of no carrier-added (NCA) 199Au through natPt(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 199Au 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 (HNO3, NH4OH). Among these extractants, the Cynaex-923 is efficient and promising for rapid separation and production of NCA 199Au from HNO3 by high extraction %. Selective extraction of 199Au from other Pt and Ir radioisotopes is observed. High recovery of 199Au 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 199Au from irradiated Pt target with high yield (99%).

Publisher

Walter de Gruyter GmbH

Subject

Physical and Theoretical Chemistry

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