A Solution-Based Approach for Mo-99 Production: Considerations for Nitrate versus Sulfate Media
Abstract
Molybdenum-99 is the parent of Technetium-99m, which is used in nearly 80% of all nuclear medicine procedures. The medical community has been plagued by Mo-99 shortages due to aging reactors, such as the NRU (National Research Universal) reactor in Canada. There are currently no US producers of Mo-99, and NRU is scheduled for shutdown in 2016, which means that another Mo-99 shortage is imminent unless a potential domestic Mo-99 producer fills the void. Argonne National Laboratory is assisting two potential domestic suppliers of Mo-99 by examining the effects of a uranyl nitrate versus a uranyl sulfate target solution configuration on Mo-99 production. Uranyl nitrate solutions are easier to prepare and do not generate detectable amounts of peroxide upon irradiation, but a high radiation field can lead to a large increase in pH, which can lead to the precipitation of fission products and uranyl hydroxides. Uranyl sulfate solutions are more difficult to prepare, and enough peroxide is generated during irradiation to cause precipitation of uranyl peroxide, but this can be prevented by adding a catalyst to the solution. A titania sorbent can be used to recover Mo-99 from a highly concentrated uranyl nitrate or uranyl sulfate solution; however, different approaches mustmore »
- Authors:
-
- Chemical Sciences and Engineering Division, Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439, USA
- Publication Date:
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1198172
- Grant/Contract Number:
- AC02-06CH11357
- Resource Type:
- Published Article
- Journal Name:
- Science and Technology of Nuclear Installations
- Additional Journal Information:
- Journal Name: Science and Technology of Nuclear Installations Journal Volume: 2013; Journal ID: ISSN 1687-6075
- Publisher:
- Hindawi Publishing Corporation
- Country of Publication:
- Egypt
- Language:
- English
Citation Formats
Youker, Amanda J., Chemerisov, Sergey D., Kalensky, Michael, Tkac, Peter, Bowers, Delbert L., and Vandegrift, George F. A Solution-Based Approach for Mo-99 Production: Considerations for Nitrate versus Sulfate Media. Egypt: N. p., 2013.
Web. doi:10.1155/2013/402570.
Youker, Amanda J., Chemerisov, Sergey D., Kalensky, Michael, Tkac, Peter, Bowers, Delbert L., & Vandegrift, George F. A Solution-Based Approach for Mo-99 Production: Considerations for Nitrate versus Sulfate Media. Egypt. https://doi.org/10.1155/2013/402570
Youker, Amanda J., Chemerisov, Sergey D., Kalensky, Michael, Tkac, Peter, Bowers, Delbert L., and Vandegrift, George F. Tue .
"A Solution-Based Approach for Mo-99 Production: Considerations for Nitrate versus Sulfate Media". Egypt. https://doi.org/10.1155/2013/402570.
@article{osti_1198172,
title = {A Solution-Based Approach for Mo-99 Production: Considerations for Nitrate versus Sulfate Media},
author = {Youker, Amanda J. and Chemerisov, Sergey D. and Kalensky, Michael and Tkac, Peter and Bowers, Delbert L. and Vandegrift, George F.},
abstractNote = {Molybdenum-99 is the parent of Technetium-99m, which is used in nearly 80% of all nuclear medicine procedures. The medical community has been plagued by Mo-99 shortages due to aging reactors, such as the NRU (National Research Universal) reactor in Canada. There are currently no US producers of Mo-99, and NRU is scheduled for shutdown in 2016, which means that another Mo-99 shortage is imminent unless a potential domestic Mo-99 producer fills the void. Argonne National Laboratory is assisting two potential domestic suppliers of Mo-99 by examining the effects of a uranyl nitrate versus a uranyl sulfate target solution configuration on Mo-99 production. Uranyl nitrate solutions are easier to prepare and do not generate detectable amounts of peroxide upon irradiation, but a high radiation field can lead to a large increase in pH, which can lead to the precipitation of fission products and uranyl hydroxides. Uranyl sulfate solutions are more difficult to prepare, and enough peroxide is generated during irradiation to cause precipitation of uranyl peroxide, but this can be prevented by adding a catalyst to the solution. A titania sorbent can be used to recover Mo-99 from a highly concentrated uranyl nitrate or uranyl sulfate solution; however, different approaches must be taken to prevent precipitation during Mo-99 production.},
doi = {10.1155/2013/402570},
journal = {Science and Technology of Nuclear Installations},
number = ,
volume = 2013,
place = {Egypt},
year = {Tue Jan 01 00:00:00 EST 2013},
month = {Tue Jan 01 00:00:00 EST 2013}
}
https://doi.org/10.1155/2013/402570
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