Related Experiment Video
Updated: Nov 1, 2025

Preparing an Isotopically Pure 229Th Ion Beam for Studies of 229mTh
Published on: May 3, 2019
Recovery of high specific activity molybdenum-99 from accelerator-induced fission on low-enriched uranium for
M Alex Brown1, Nathan Johnson2, Artem V Gelis3
1Chemical and Fuel Cycle Technologies, Argonne National Laboratory, 9700 S Cass Ave, Lemont, IL, 60439, USA.
Abstract:
A new process was developed to recover high specific activity (no carrier added) 99Mo from electron-accelerator irradiated U3O8 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.
Related Concept Videos
Nuclear Transmutation
Nuclear Power
Nuclear Fuels
Nuclear fuel consists of a fissile isotope, such as uranium-235, which must be present in sufficient quantity to provide a...

