Research Progress on Cr-Coated Zirconium Alloy Cladding of Accident Tolerant Fuel

Abstract:

Accident tolerant fuel (ATF) can further improve the safety and economics of commercial nuclear reactors. At present, Cr-coated zirconium alloy cladding is the most promising candidate for near-term industrial application as an ATF cladding. This paper provides a comprehensive review of Cr-coated zirconium alloy cladding, covering its development status, preparation processes, microstructural characteristics, and service performance. Initially, the worldwide development of Cr coating is introduced. Subsequently, the main preparation processes of Cr coatings, including cold spraying, laser cladding, and physical vapor deposition, are described, and the characteristics and microstructure of different processes are analyzed. Afterwards, the corrosion, irradiation, and mechanical properties of Cr-coated zirconium alloy cladding are summarized, and the corrosion oxidation mechanism, irradiation damage mechanism, and plastic deformation mechanism are deeply analyzed. Finally, the key challenges in current research are identified, and future development directions are proposed.