Document Type
Article
Publication Date
6-24-2021
Publication Title
Scientific Reports
Volume
11
Issue
1
First page number:
1
Last page number:
7
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.
Disciplines
Biological and Chemical Physics | Physical Chemistry
File Format
File Size
1173 KB
Language
English
Rights
IN COPYRIGHT. For more information about this rights statement, please visit http://rightsstatements.org/vocab/InC/1.0/
Creative Commons License
This work is licensed under a Creative Commons Attribution 4.0 License.
Repository Citation
Brown, M.,
Johnson, N.,
Gelis, A.,
Stika, M.,
Servis, A.,
Bakken, A.,
Krizmanich, C.,
Shannon, K.,
Kozak, P.,
Barnhart, A.,
Denbrock, C.,
Luciani, N.,
Grimm, T.,
Tkac, P.
(2021).
Recovery of High Specific Activity Molybdenum-99 From Accelerator-Induced Fission on Low-Enriched Uranium for Technetium-99m Generators.
Scientific Reports, 11(1),
1-7.
http://dx.doi.org/10.1038/s41598-021-92704-z
Comments
The original version of this Article contained an error in the copyright line.
“© The Author(s) 2021” now reads: “© UChicago Argonne, LLC, Operator of Argonne National Laboratory, Niowave Inc, and the Author 2021”
The original Article has been corrected.