Lead-cooled Fast Reactors (LFRs) are among the Generation IV reactor concepts currently being investigated for their favourable thermal-hydraulic and neutronic characteristics. The use of lead-bismuth eutectic (LBE) as coolant, combined with the flexibility and enhanced safety features of Small Modular Reactors (SMRs), makes these systems attractive candidates for future nuclear energy production. The design and optimisation of such reactors require accurate thermal-hydraulic analyses capable of predicting coolant flow behaviour, heat transfer mechanisms, and pressure losses throughout the reactor core. However, full-core Computational Fluid Dynamics (CFD) simulations of wire-wrapped fuel assemblies remain extremely demanding from a computational standpoint due to the large disparity between the small geometric features governing local flow phenomena and the overall dimensions of the reactor core.