A chemical process for the separation and purification of fission product "Mo by the irradiation of natural U0 2 targets has been developed. The major separation steps include: (1) Extraction of "Mo with 5% D2EHPA (Di-2-Ethylhexyl Phosphoric Acid)/ kerosene from a nitric acid solution (2) Removal of H 2 0 2 in a dilute acid medium with a platinum catalyst (3) Initial purification of "Mo by alumina adsorption, and (4) Final purification of "Mo by calcium phosphate hydroxide adsorption. Variables affecting on the chemical yield and purity of "Mo in each process step were examined in batch studies. A full-scale synthetic solution experiment with the established optimum process conditions was carried out in a hot cell. It is estimated that 20 to 70 curies of "Mo can be obtained by irradiating about 400 grams of natural UO, target at TRR (Taiwan Research Reactor) with a neutron flux of 5 X 10' 3 n/cm 2 /sec. The calculated specific activity of the "Mo product solution is 6 X 10 2 to 3 X 10 3 Ci/g and its estimated radionuclide purity and other quality assay were extremely satisfactory. The experimental results indicated that this separated high specific activity of "Mo is suitable for the preparation of " m Tc generator for nuclear medical applications.
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