Monte Carlo neutron photon code analyses of compacted fuel storage

Because the N Reactor and the plutonium/uranium extraction (PUREX) chemical separations plant have been shut down, the N Reactor fuel needs to be stored until ultimate disposition has been identified. Compacted storage of fuel in a single basin is considered a cost-effective alternative. This paper discusses criticality safety evaluations of compacted fuel storage options and possible accident scenarios associated with them. The analyses were performed using the Monte Carlo neutron photon (MCNP) code on a SUN workstation. The calculations demonstrate the MCNP code's ability to address a variety of criticality safety issues. The results of the analyses are shown. The criticality limit for the basin of keff = 0.98 was not exceeded for any of the accidents. Two very important criticality control features were the material of the canister an the canister's ability to contain fuel