Application of burnup credit to preserve spent fuel storage space

Abstract

This study delves into the complexities of burnup credit, exploring area savings (ΔA) achieved by taking credit for different nuclide groups compared to fresh fuel and their implications on reactivity within Spent Nuclear Fuel (SNF) cask storage. The project investigated the benefit of burnup credit using a structured 2 x 2 spent fuel storage matrix for the SNF casks, conducting a thorough analysis of the effective multiplication factor (keff) at different areas occupied by the SNF casks utilizing the SCALE code, a robust nuclear analysis software suite. Fresh fuel served as a keff benchmark, with major actinides exhibiting modest reactivity and space savings, while actinides plus principal fission products highlighted substantial space savings alongside the highest reactivity savings. This analysis provides crucial insights for optimizing SNF storage capacity using burnup credit to achieve area savings in cask storage. The research underscores the pivotal role of burnup credit in enhancing efficiency and safety in SNF cask storage, offering valuable perspectives for advancing nuclear fuel management practices.