Neutronic evaluation of initial NuScale-like core loaded with reprocessed fuel

Abstract

The present study evaluates the potential insertion of reprocessed fuel in a NuScale-like core. The main idea consists of assessing the beginning of life (BOL) safety parameters of the core loaded with reprocessed fuel and comparing them to the reference case using conventional uranium-based fuel. Two different reprocessed fuels were studied: one of them reprocessed using the GANEX process, while the other one used the UREX+ process. Overall, the cases in which the core was simulated with reprocessed fuel achieved better results than conventional UO2 for fuel temperature coefficient and normalized peak factor. Furthermore, the usage of reprocessed fuel could also reduce the dependence on chemical control for reactivity, which is a desired condition in the event of borated water unavailability. The Serpent code version 2.1.32 developed by VTT was used to perform the simulations.