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Review on the Preparation and High-Temperature Oxidation Resistance of Metal Coating for Fuel Cladding Zirconium Alloys

Ling Sun, Yuchen Xiao, Weijiu Huang, Baifeng Luan, Baoan Wu, Huiyi Tang

Nuclear Science and Engineering / Volume 198 / Number 4 / April 2024 / Pages 755-770

Research Article / dx.doi.org/10.1080/00295639.2023.2219802

Received:March 14, 2023
Accepted:May 20, 2023
Published:February 28, 2024

Zirconium alloys have outstanding nuclear properties and are irreplaceable key materials for the development of nuclear power systems. The preparation of coatings on the surface of zirconium alloys is one of the potential solutions of fuel cladding materials. In this paper, the research progress of the preparation and high-temperature oxidation resistance of metal coating for fuel cladding zirconium alloys is reviewed, which includes the preparation method, coating-type selection, high-temperature oxidation resistance, and high-temperature oxidation failure mechanism of different coatings. This review provides important references for the development of fuel cladding zirconium alloy surface coating technology.