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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.

Recovery of high specific activity molybdenum-99 from accelerator-induced fission on low-enriched uranium for technetium-99m generators