Sorbent Selection Progress Report

Stepinski, Dominique C.; Ziegler, A.; Jerden, James L.; Fortner, J.; Quigley, Kevin; Mertz, Carol J.; Gelis, Artem V.; Chemerisov, Sergey; Tsai, Yifen; Bakel, A. J.; Vandegrift, G. F.; Chun, Pu; Wang, L.

doi:10.2172/1121039

Cited by 4 publications

(9 citation statements)

References 7 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Based on the batch data shown above, the Mo-recovery column is going to be larger for the SHINE system due to competition from sulfate. Table 2 shows , which will not adsorb on the Mo-recovery column [1,9,20,27,33,34]. Because both MIPS and SHINE will be recycling their fuel/target solutions, adding an oxidant is not trivial.…”

Section: Plant-scale Columnmentioning

confidence: 99%

“…Previous experiments with irradiated solutions showed that iodine contaminates the Mo-99 product prior to entry into the purification process. Iodine contamination in the Mo-99 product partially comes from decay of several Te isotopes, Te adsorbs, and Mo on a titania sorbent [9]. The distribution of isotopes during the separation and recovery processes is important for waste classification purposes.…”

Section: Plant-scale Columnmentioning

confidence: 99%

“…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%

See 3 more Smart Citations

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

View full text Add to dashboard Cite

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.

show abstract

Section: Plant-scale Columnmentioning

confidence: 99%

Section: Plant-scale Columnmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

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

View full text Add to dashboard Cite

show abstract

“…They offer high capacity and remarkable K d values, and are slightly affected by the presence of uranium. Their superior performance in the presence of high concentrations of uranium contrasts that of alumina (Stepinski et al 2008(Stepinski et al , 2009. The Mo K d for alumina decreases dramatically in the presence of high concentrations of uranium, making it unsuitable for the recovery of Mo from highly concentrated uranium solutions.…”

Section: Introductionmentioning

confidence: 99%

Design of Column Separation Processes for Recovery of Molybdenum from Dissolved High-Density LEU Target

Stepinski¹,

Krahn²,

Chung³

2011

View full text Add to dashboard Cite

Controlling Pu behavior on Titania: Implications for LEU Fission-Based Mo-99 Production

Youker

Brown

Heltemes

et al. 2017

Ind. Eng. Chem. Res.

View full text Add to dashboard Cite

Molybdenum-99 is the parent isotope of the most widely used isotope, technetium-99m, in all diagnostic nuclear medicine procedures. Due to proliferation concerns associated with the use of highly enriched uranium (HEU), the preferred method of fission-based Mo-99 production uses low enriched uranium (LEU) targets. Using LEU versus HEU for Mo-99 production produces ∼30 times more Pu-239, due to neutron capture on U-238 to produce Np-239, which ultimately decays to Pu-239 (t 1/2 = 24,110 yr). Argonne National Laboratory is supporting a potential US Mo-99 producer in their efforts to produce Mo-99 from an LEU solution. In order to mitigate the generation of large volumes of greater-than-class-C (GTCC) low level waste (Pu-239 concentrations greater than 1 nCi/g), we have focused our efforts on the separation chemistry of Pu and Mo with a titania sorbent in sulfate media. Results from batch and column experiments show that temperature and acid wash concentration can be used to control Pu behavior on titania.

show abstract

Sorbent Selection Progress Report

Cited by 4 publications

References 7 publications

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

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

Design of Column Separation Processes for Recovery of Molybdenum from Dissolved High-Density LEU Target

Controlling Pu behavior on Titania: Implications for LEU Fission-Based Mo-99 Production

Contact Info

Product

Resources

About