Application and Development Progress of Cr-Based Surface Coatings in Nuclear Fuel Element: I. Selection, Preparation, and Characteristics of Coating Materials

被引:60
作者
Chen, Huan [1 ]
Wang, Xiaoming [1 ]
Zhang, Ruiqian [1 ]
机构
[1] Nucl Power Inst China, Chengdu 610200, Peoples R China
关键词
zirconium alloy; accident-tolerant fuel; ATF cladding material; surface coating; coating preparation; ACCIDENT-TOLERANT FUEL; HIGH-TEMPERATURE OXIDATION; ZIRCONIUM-ALLOY; CHROMIUM COATINGS; DLI-MOCVD; COATED ZIRCALOY-4; MAX PHASES; BEHAVIOR; IRRADIATION; STEAM;
D O I
10.3390/coatings10090808
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
To cope with the shortcomings of nuclear fuel design exposed during the Fukushima Nuclear Accident, researchers around the world have been directing their studies towards accident-tolerant fuel (ATF), which can improve the safety of fuel elements. Among the several ATF cladding concepts, surface coatings comprise the most promising strategy to be specifically applied in engineering applications in a short period. This review presents a comprehensive introduction to the latest progress in the development of Cr-based surface coatings based on zirconium alloys. Part I of the review is a retrospective look at the application status of zirconium alloy cladding, as well as the development of ATF cladding. Following this, the review focuses on the selection process of ATF coating materials, along with the advantages and disadvantages of the current mainstream preparation methods of Cr-based coatings worldwide. Finally, the characteristics of the coatings obtained through each method are summarized according to some conventional performance evaluations or investigations of the claddings. Overall, this review can help assist readers in getting a thorough understanding of the selection principle of ATF coating materials and their preparation processes.
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页数:25
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