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Title: 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 » be taken to prevent precipitation during Mo-99 production.« less

Authors:
 [1];  [1];  [1];  [1];  [1];  [1]
  1. 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. doi: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. doi: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 = {2013},
month = {1}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record
DOI: 10.1155/2013/402570

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Cited by: 2 works
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