Generation IV nuclear fission systems are being developed to improve the sustainability, safety and long term performance of nuclear energy. Among these systems, Lead cooled Fast Reactors are of particular interest because liquid lead combines a high boiling point, good heat removal capability and favourable neutronic properties, allowing operation at high temperature and near atmospheric pressure. These features make lead a promising coolant for advanced reactor concepts, while also requiring accurate thermal hydraulic modelling of the heat transfer processes in components such as steam generators. In this context, reliable heat transfer correlations for liquid metal flow in representative geometries and operating conditions are needed to support the assessment and design of LFR steam generator configurations.