Skip to main content

Fast Flux Test Facility (FFTF) Reactor Fuel Criticality Calculations

L. M. Montierth
Publication Date


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 intact fuels for the pre-closure time frame and provide input for canister design. The calculational method employed in this calculation is to use the MCNP Version 4B2 computer code (Ref. 7.1) to calculate the effective multiplication factor (k-eff) for various geometrical configurations of FFTF fuel.

Category of Content
Associated Sites