Data from calculations of radial distribution of neutron flux per emitted neutron from rods of spent nuclear fuel in a KBS-3 type geological repository. Reference (Jansson, 2022) contain a summary of
Abstract The present work focuses on a pre-equilibrium nuclear reaction code (based on the one, two and infinity hypothesis of pre-equilibrium nuclear reactions). In the PHASE-OTI code, pre-equilibr
These data contain the Serpent and RAPID transport calculation results on the BEAVRS benchmark with four distributions of temperature, including: 1. Only heterogeneous fuel temperature 2. Only hetero
