The document describes a proposed design for a spent nuclear fuel transport cask to transfer used fuel assemblies from the Sizewell B nuclear power plant in England to a reprocessing facility. The cask uses multiple layers of shielding materials like depleted uranium concrete and steel alloys to safely contain radiation and prevent leakage. It is designed to withstand drops from heights of up to 9 meters based on finite element analysis testing. The cask would allow for the safe transportation of 50 fuel assemblies per year via a 1.4 mile road journey followed by rail to meet regulatory weight and size limits for transport.