摘要：A new process was developed to recover high specific activity (no carrier added)
99Mo from electron-accelerator irradiated U
3O
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
99Mo intended for making
99Mo/
99mTc generators. The process was demonstrated with irradiated uranium targets resulting in more than 95%
99Mo recovery and without presence of fission products or actinides in the product.
