A Solution-Based Approach for Mo-99 Production: Considerations for Nitrate versus Sulfate Media

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-9...

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Main Authors: Amanda J. Youker, Sergey D. Chemerisov, Michael Kalensky, Peter Tkac, Delbert L. Bowers, George F. Vandegrift
Format: Article
Language:English
Published: Wiley 2013-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2013/402570
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author Amanda J. Youker
Sergey D. Chemerisov
Michael Kalensky
Peter Tkac
Delbert L. Bowers
George F. Vandegrift
author_facet Amanda J. Youker
Sergey D. Chemerisov
Michael Kalensky
Peter Tkac
Delbert L. Bowers
George F. Vandegrift
author_sort Amanda J. Youker
collection DOAJ
description 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.
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series Science and Technology of Nuclear Installations
spelling doaj-art-058a5bd75a2e42fda52367852d853b3d2025-02-03T05:46:46ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832013-01-01201310.1155/2013/402570402570A Solution-Based Approach for Mo-99 Production: Considerations for Nitrate versus Sulfate MediaAmanda J. Youker0Sergey D. Chemerisov1Michael Kalensky2Peter Tkac3Delbert L. Bowers4George F. Vandegrift5Chemical Sciences and Engineering Division, Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439, USAChemical Sciences and Engineering Division, Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439, USAChemical Sciences and Engineering Division, Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439, USAChemical Sciences and Engineering Division, Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439, USAChemical Sciences and Engineering Division, Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439, USAChemical Sciences and Engineering Division, Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439, USAMolybdenum-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.http://dx.doi.org/10.1155/2013/402570
spellingShingle Amanda J. Youker
Sergey D. Chemerisov
Michael Kalensky
Peter Tkac
Delbert L. Bowers
George F. Vandegrift
A Solution-Based Approach for Mo-99 Production: Considerations for Nitrate versus Sulfate Media
Science and Technology of Nuclear Installations
title A Solution-Based Approach for Mo-99 Production: Considerations for Nitrate versus Sulfate Media
title_full A Solution-Based Approach for Mo-99 Production: Considerations for Nitrate versus Sulfate Media
title_fullStr A Solution-Based Approach for Mo-99 Production: Considerations for Nitrate versus Sulfate Media
title_full_unstemmed A Solution-Based Approach for Mo-99 Production: Considerations for Nitrate versus Sulfate Media
title_short A Solution-Based Approach for Mo-99 Production: Considerations for Nitrate versus Sulfate Media
title_sort solution based approach for mo 99 production considerations for nitrate versus sulfate media
url http://dx.doi.org/10.1155/2013/402570
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