Development of non-carrier added Au-199 production procedure from neutron-irradiated Pt targets

Au-199 has appropriate characteristics to be used for single photon emission computed tomography (SPECT) imaging and/or targeted beta radionuclide therapy. This study focuses on production of non-carrier added Au-199 via radiochemical separation from a Pt target with natural isotopic composition, which has been irradiated in a nuclear reactor. The separation procedure for the separation of Au and Pt using commercially available TBP resin was developed first with stable Au and Pt. Then, the Pt dissolution procedure was optimized. This was followed by test irradiations of Pt targets to assess irradiation yields for Au-199 and to identify radionuclidic impurities. Irradiation yields obtainable by medium-flux and high-flux research reactors were assessed and compared. Finally, the separation procedure was applied to separate Au-199 from irradiated Pt targets. The achieved irradiation yield was up to 485 GBq/g of Pt target. The Au-199 separation efficiency for ∼11 mg Pt targets achieved was 78 % with no radionuclidic impurities, except Au-198 detected. The results indicate that the production of Au-199 activities sufficient for imaging applications is feasible by irradiation of Pt targets with natural isotopic composition in medium-flux reactors. Higher activities for therapeutic applications are more efficiently produced in high-flux reactors.