Author:
Brown M. Alex,Johnson Nathan,Gelis Artem V.,Stika Milan,Servis Anna G.,Bakken Alex,Krizmanich Christine,Shannon Kristin,Kozak Peter,Barnhart Amanda,Denbrock Chad,Luciani Nicolas,Grimm Terry,Tkac Peter
Abstract
AbstractA 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.
Funder
National Nuclear Security Administration
Publisher
Springer Science and Business Media LLC
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