Abstract:Accident tolerant fuel can further improve the safety and economics of commercial nuclear reactors. At present, Cr coating improved zirconium alloy cladding is the best solution for accident tolerant fuel cladding that can achieve industrial application in the short term. This paper reviews the research progress of Cr-coated zirconium alloy cladding, starting from the development status, preparation process, microstructure and service performance of Cr-coated zirconium alloy cladding. Firstly, the development of Cr coating at home and abroad is introduced. Secondly, the main preparation processes of Cr coatings, including cold spraying, laser cladding and physical vapor deposition, were described, and the characteristics and microstructure of different processes were analyzed. Then, the corrosion properties, irradiation properties 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 problems existing in the current research and the future development direction are analyzed and prospected.