Abstract
A new process was developed to recover high specific activity (no carrier added) (99)Mo from electron-accelerator irradiated U(3)O(8) or uranyl sulfate targets. The process leverages a novel solvent extraction scheme to recover Mo using di(2-ethylhexyl) phosphoric acid following uranium and transuranics removal with tri-n-butyl phosphate. An anion-exchange concentration column step provides a final purification, generating pure (99)Mo intended for making (99)Mo/(99m)Tc generators. The process was demonstrated with irradiated uranium targets resulting in more than 95% (99)Mo recovery and without presence of fission products or actinides in the product.