包层(金属加工)
锆
材料科学
锆合金
涂层
核燃料
冶金
合金
金属
复合材料
核化学
化学
作者
Ling Sun,Yuchen Xiao,Weijiu Huang,Baifeng Luan,Baoan Wu,Huiping Tang
标识
DOI:10.1080/00295639.2023.2219802
摘要
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.
科研通智能强力驱动
Strongly Powered by AbleSci AI