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Fast Flux Test Facility (FFTF) Reactor Fuel Degraded Criticality Calculation: Intact SNF Canister

L. M. Montierth
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The purpose of these calculations is to characterize the criticality safety concerns for the storage of Fast Flux Test Facility (FFTF) nuclear fuel in a Department of Energy spent nuclear fuel (DOE SNF) canister in a co-disposal waste package. These results will be used to support the analysis that will be done to demonstrate concept viability related to use in the Monitored Geologic Repository (MGR) environment. The calculations presented here are to be used to evaluate the criticality issues related to these degraded fuels for the post-closure time frame and provide input for canister design.

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