Effect of Corrosion Behavior on the Heat Transfer Performance of Fuel Cladding in Lead-Cooled Fast Reactors

Abstract In lead-cooled fast reactors, preventing corrosion of materials like stainless steel by liquid metal is crucial. The protective oxide film on stainless steel surfaces, formed to mitigate corrosion in lead/lead-bismuth systems, can, paradoxically, degrade heat transfer in cladding during high-oxygen concentration or normal operation. This study investigates the impact of corrosion on heat transfer, focusing on steady-state conditions. By analyzing temperature changes with and without corrosion, the study aims to understand the balance between oxide film formation and heat conduction. Additionally, it assesses corrosion effects under accident conditions to enhance safety in lead-cooled fast reactors. The findings contribute valuable insights for designing and operating cooling systems, ensuring the safety and reliability of nuclear energy systems.