Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage

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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“…Adapted from [34] with copyright permission from Elsevier. More information found in [11,[35][36][37][38][42][43][44].…”

Section: Current Status Of Application Of Zirconium Alloy Claddingsmentioning

confidence: 99%

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

2020

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Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube

Kim

Woo

Lee

2022

Journal of Nuclear Materials

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Accurate prediction of threshold stress for hydride reorientation in Zircaloy-4 with directly measured interface orientation relationship

2022

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Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage

Cited by 3 publications

References 14 publications

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

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

Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube

Accurate prediction of threshold stress for hydride reorientation in Zircaloy-4 with directly measured interface orientation relationship

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