Mo-99 Stripping Results and Column Designs for Mini-Medical Isotope Production System (MIPS)

Youker, Amanda J.; Chung, Ping-Ting; Krahn, E.; Stepinski, Dominique C.; Gelis, Artem V.

doi:10.2172/1132240

Cited by 2 publications

(3 citation statements)

References 2 publications

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“…The diffusivities of Te and Zr are assumed to be the same as that of Mo, which has been published previously [2]. The diffusivity of NaOH was obtained previously as well [3].…”

Section: Introductionmentioning

confidence: 99%

VERSE Simulations and Experiments of Competing Components in Molybdenum Adsorption and Recovery Process

Youker¹,

Stepinski²,

Vandegrift³

et al. 2014

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“…The diffusivities of Te and Zr are assumed to be the same as that of Mo, which has been published previously [2]. The diffusivity of NaOH was obtained previously as well [3].…”

Section: Introductionmentioning

confidence: 99%

VERSE Simulations and Experiments of Competing Components in Molybdenum Adsorption and Recovery Process

Youker¹,

Stepinski²,

Vandegrift³

et al. 2014

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“…SHINE Medical Technologies is developing Subcritical Hybrid Intense Neutron Emitter (SHINE), which is an accelerator-driven process that will use an LEU uranyl sulfate target solution for Mo-99 production [2,3]. For these systems, Argonne has developed a Mo-recovery process for either the irradiated uranyl sulfate or uranyl nitrate solution using a titania sorbent [4][5][6][7][8][9][10][11][12][13][14][15][16].…”

Section: Introductionmentioning

confidence: 99%

“…This is most easily seen by comparing Mo(VI) partitioning between the solutions and the titania sorbent [4,8,[13][14][15]20]. However, plant-scale separation columns have been designed for both MIPS and SHINE systems [8,9,[12][13][14][15]. A general comparison of the two recovery operations will be discussed below.…”

Section: Introductionmentioning

confidence: 99%

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

Youker

Chemerisov

Kalensky

et al. 2013

Science and Technology of Nuclear Installations

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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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Mo-99 Stripping Results and Column Designs for Mini-Medical Isotope Production System (MIPS)

Cited by 2 publications

References 2 publications

VERSE Simulations and Experiments of Competing Components in Molybdenum Adsorption and Recovery Process

VERSE Simulations and Experiments of Competing Components in Molybdenum Adsorption and Recovery Process

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

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