Abstract
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.
Highlights
The nuclear fuel element is the core component of a nuclear reactor that plays a role in releasing heat and tolerating fission gas [1]
A more detailed critical review is presented that focuses on the latest progress in the development of Cr-based surface coatings on zirconium alloys employed in accident-resistant fuel elements
The aim was to simultaneously improve high-temperature steam oxidation resistance and high-temperature mechanical properties of Zr alloy claddings. The results in their out-of-reactor performance research showed that a CrAl coating exhibited dual excellent performance under normal and accident conditions; the creep resistance of a Zr alloy cladding subjected to the surface oxide dispersion-strengthened (ODS) strengthening treatment at 380 ◦ C and its anti-ballooning/bursting performance in a loss-of-coolant accidents (LOCAs) simulation test were both notably improved compared to the results obtained for the coating without ODS treatment [34]
Summary
The nuclear fuel element is the core component of a nuclear reactor that plays a role in releasing heat and tolerating fission gas [1]. Surface coatings are the technological trend of modifying zirconium alloy to enhance accident tolerance without causing significant changes to the existing UO2 /Zr alloy cladding fuel design that has been extensively used in commercial water-cooled reactors, thereby holding tremendous application prospects [13]. Researchers from the non-nuclear field do not have a clear understanding of the application background of ATF coating materials, which impedes the development of related research. To fill this gap, a more detailed critical review is presented that focuses on the latest progress in the development of Cr-based surface coatings on zirconium alloys employed in accident-resistant fuel elements. It clarifies the adaptability of various coating systems under the operating environment of a reactor, the advantages and disadvantages of the current mainstream preparation methods of Cr-based coatings around the world, and the characteristics of coatings prepared by each method
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