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Design of the Phase-2 Target for Mini-SHINE/MIPS Experiments.

DE141132253

Publication Date	2012
Personal Author	Chemerisov, S.; Bailey, J.; Makarashvili, V.; Micklich, B.; Vandegrift, G. J.
Page Count	26
Abstract	Under the National Nuclear Security Administration's Global Threat Reduction Initiative (GTRI), Argonne National Laboratory (Argonne) is assisting three potential domestic producers to develop and implement molybdenum-99 (Mo-99) production in the United States without the use of highly enriched uranium (HEU). Two of the potential domestic producers are Babcock and Wilcox Technical Services Group (B&W) and Morgridge Institute for Research (MIR). B&W is developing the Medical Isotope Production System (MIPS). In this system, the Mo-99 is produced in an LEU-fueled Aqueous Homogenous Reactor (AHR) by the fissioning of uranium-235 (U-235). The MIPS consists of an AHR containing a low enriched uranium (LEU) solution, a molybdenum-extraction system utilizing a chromatographic column, and a reactor off-gas and solution-control systems. The use of AHRs presents an attractive alternative to the conventional target-irradiation method for producing Mo-99 because the fuel solution itself is used to produce Mo-99, eliminating the need for targets. AHRs also operate at a much lower power level than that required for a traditional reactor. The three areas of Argonne research and development (R&D) are (1) radiolytic-gas generation in the fuel solution, (2) effects of fission and radiation on reactor-solution chemistry, and (3) development and optimization recovery of molybdenum from the irradiated fuel solution.
Keywords	Isotope production Nuclear medicine Aqueous homogeneous reactors Fuels Highly enriched urnanium Implementation Irradiation Molybdenum 99 Optimization Production Research and development Targets
Source Agency	Technical Information Center Oak Ridge Tennessee
NTIS Subject Category	77B - Isotopes 77H - Reactor Engineering & Nuclear Power Plants
Corporate Authors	Argonne National Lab., IL.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	201425

Design of the Phase-2 Target for Mini-SHINE/MIPS Experiments.

Design of the Phase-2 Target for Mini-SHINE/MIPS Experiments.
DE141132253

Publication Date	2012
Personal Author	Chemerisov, S.; Bailey, J.; Makarashvili, V.; Micklich, B.; Vandegrift, G. J.
Page Count	26
Abstract	Under the National Nuclear Security Administration's Global Threat Reduction Initiative (GTRI), Argonne National Laboratory (Argonne) is assisting three potential domestic producers to develop and implement molybdenum-99 (Mo-99) production in the United States without the use of highly enriched uranium (HEU). Two of the potential domestic producers are Babcock and Wilcox Technical Services Group (B&W) and Morgridge Institute for Research (MIR). B&W is developing the Medical Isotope Production System (MIPS). In this system, the Mo-99 is produced in an LEU-fueled Aqueous Homogenous Reactor (AHR) by the fissioning of uranium-235 (U-235). The MIPS consists of an AHR containing a low enriched uranium (LEU) solution, a molybdenum-extraction system utilizing a chromatographic column, and a reactor off-gas and solution-control systems. The use of AHRs presents an attractive alternative to the conventional target-irradiation method for producing Mo-99 because the fuel solution itself is used to produce Mo-99, eliminating the need for targets. AHRs also operate at a much lower power level than that required for a traditional reactor. The three areas of Argonne research and development (R&D) are (1) radiolytic-gas generation in the fuel solution, (2) effects of fission and radiation on reactor-solution chemistry, and (3) development and optimization recovery of molybdenum from the irradiated fuel solution.
Keywords	Isotope production Nuclear medicine Aqueous homogeneous reactors Fuels Highly enriched urnanium Implementation Irradiation Molybdenum 99 Optimization Production Research and development Targets
Source Agency	Technical Information Center Oak Ridge Tennessee
NTIS Subject Category	77B - Isotopes 77H - Reactor Engineering & Nuclear Power Plants
Corporate Authors	Argonne National Lab., IL.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	201425