Preliminary studies of used fuel generated in the US Department of Energy’s Advanced Fuel Cycle Initiative have indicated that current used fuel transport casks may be insufficient for the transportation of said fuel. This work considers transport of three 5-year-cooled oxide Advanced Burner Reactor used fuel assemblies with a burn-up of 160 MWD/kg. A transport cask designed to carry these assemblies is proposed. This design employs a 7-cm-thick lead gamma shield and a 20-cm-thick NS-4-FR composite neutron shield. The temperature profile within the cask, from its center to its exterior surface, is determined by two dimensional computational fluid dynamics simulations of conduction, convection, and radiation within the cask. Simulations are performed for a cask with a smooth external surface and various neutron shield thicknesses. Separate simulations are performed for a cask with a corrugated external surface and a neutron shield thickness that satisfies shielding constraints. Resulting temperature profiles indicate that a three-assembly cask with a smooth external surface will meet fuel cladding temperature requirements but will cause outer surface temperatures to exceed the regulatory limit. A cask with a corrugated external surface will not exceed the limits for both the fuel cladding and outer surface temperatures.
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ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference
July 18–22, 2010
Bellevue, Washington, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-4926-2
PROCEEDINGS PAPER
Thermal Analysis of a Proposed Transport Cask for Three Advanced Burner Reactor Used Fuel Assemblies Available to Purchase
Miles Greiner,
Miles Greiner
University of Nevada, Reno, NV
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Matt Dennis,
Matt Dennis
Sandia National Labs, Albuquerque, NM
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Samuel Bays,
Samuel Bays
Idaho National Lab, Idaho Falls, ID
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Ruth Weiner
Ruth Weiner
Sandia National Labs, Albuquerque, NM
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Tim Bullard
University of Nevada, Reno, NV
Miles Greiner
University of Nevada, Reno, NV
Matt Dennis
Sandia National Labs, Albuquerque, NM
Samuel Bays
Idaho National Lab, Idaho Falls, ID
Ruth Weiner
Sandia National Labs, Albuquerque, NM
Paper No:
PVP2010-26138, pp. 579-586; 8 pages
Published Online:
January 10, 2011
Citation
Bullard, T, Greiner, M, Dennis, M, Bays, S, & Weiner, R. "Thermal Analysis of a Proposed Transport Cask for Three Advanced Burner Reactor Used Fuel Assemblies." Proceedings of the ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASME 2010 Pressure Vessels and Piping Conference: Volume 7. Bellevue, Washington, USA. July 18–22, 2010. pp. 579-586. ASME. https://doi.org/10.1115/PVP2010-26138
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