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- W1481253546 abstract "The spent fuel carrying capacities of previous generation shipping casks have been primarily thermal and/or shielding limited. Shielding and heat transfer requirements for casks designed to transport older spent fuel with longer decay times are reduced significantly. Thus, a considerable weight margin is available to the designer for increasing the payload capacity. One method of achieving an increase in capacity is by reducing fuel assembly spacing. The amount of reduction in assembly spacing available is limited by criticality and fuel support structural concerns. The optimum fuel assembly spacing achievable is then limited by requirements to both control neutron multiplication and ensure the structural integrity of fuel support components. An investigation of the feasibility of accounting for fuel burnup in the design of spent fuel shipping casks was recently completed for the US Department of Energy's Office of Civilian Radioactive Waste Management (OCRWM). The purpose of this presentation is to describe the results of the criticality analyses and briefly summarize potential impacts in terms of increased cask capacities with associated costs and safety benefits. The scope of the analysis is limited to typical burnups of full-cycle, discharged pressurized water reactor (PWR) fuel and generic shipping cask designs. The burnup and criticalitymore » analyses were performed with various SCALE system modules: ORIGEN-S, NITAWL-S, XSDRNPM, KENO V.a, and the SCALE 22 group ENDF/B-IV cross section library enchanced with ENDF/B-V fission produced data. 3 refs., 1 fig.« less" @default.
- W1481253546 created "2016-06-24" @default.
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- W1481253546 date "1987-05-01" @default.
- W1481253546 modified "2023-09-27" @default.
- W1481253546 title "Burnup credit in the design of spent-fuel shipping casks" @default.
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