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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
A wave of new U.S.-U.K. deals ahead of Trump’s state visit
President Trump will arrive in the United Kingdom this week for a state visit that promises to include the usual pomp and ceremony alongside the signing of a landmark new agreement on U.S.-U.K. nuclear collaboration.
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 | doi.org/10.1080/00295639.2023.2219802
Articles are hosted by Taylor and Francis Online.
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.