Preparation and high-temperature oxidation resistance of zirconium alloys

Researchers from the National Engineering Research Center for Instrument Functional Materials and Chongqing University, both in Chongqing, China, have highlighted the pivotal role of zirconium alloys in nuclear power systems. Their latest paper reviews the significant advancements in coating technologies for zirconium alloy fuel cladding, a crucial component in nuclear reactors. The study discusses various preparation methods, types of coatings, and their efficacy in resisting high-temperature oxidation—a key challenge for fuel cladding materials. This comprehensive review aims to serve as a critical reference in advancing the surface coating technology of fuel cladding zirconium alloys, promising enhanced performance and safety in nuclear power applications.

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