A Solution-Based Approach for Mo-99 Production: Considerations for Nitrate versus Sulfate Media. (10th September 2013)

• Record Type: Journal Article
• Authors: Youker, Amanda J.; Chemerisov, Sergey D.; Kalensky, Michael; Tkac, Peter; Bowers, Delbert L.; Vandegrift, George F.
• Other Names: Ahmad Mushtaq Academic Editor.
• Is Part Of: Science and technology of nuclear installations. Volume 2013(2013)
• Publication Date: 2013-09-10
• Subjects: Nuclear engineering -- Periodicals; Nuclear facilities -- Periodicals; Nuclear engineering; Nuclear facilities; Electronic journals; Periodicals; 621.48
• DOI: 10.1155/2013/402570
• Languages: English
• ISSNs: 1687-6075

Abstract

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 must be taken to prevent precipitation during Mo-99 production.