Out-of-pile performance of surface-modified Zr cladding for accident tolerant fuel in LWRs

Kim, Hyung-Il; Kim, Il-Hyun; Jung, Yang‐Il; Park, Dong-Jun; Park, Jung Hwan; Choi, Bong Hyuk; Lee, Young-Ho

doi:10.1016/j.jnucmat.2018.07.061

Cited by 66 publications

(21 citation statements)

References 11 publications

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“…The performance of zirconium alloy cladding during the fuel cycle is summarized in Table 1 [33,34]. Under normal operating conditions, the use of commercial zirconium alloy claddings can usually meet the significant performance requirements of existing reactors for resistance to corrosion, creep, irradiation growth, and abrasion [35][36][37].…”

Section: Current Status Of Application Of Zirconium Alloy Claddingsmentioning

confidence: 99%

“…Performance of the commercial zirconium alloy cladding during the fuel cycle. 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%

“…[51,56,[66][67][68], which can completely replace zirconium alloys. The other route is to prepare coatings on the surface of the existing zirconium alloy claddings [13,33,34,[69][70][71][72][73][74]. According to the ATF R&D plans of various countries in the world [75][76][77][78], different research institutes have focused on the R&D directions of ATF claddings.…”

Section: Proposal and Development Of Atf Claddingmentioning

confidence: 99%

“…Compared to the above-mentioned Al-containing coatings, the dissolution of FeCrAl alloy and CrAl alloy coatings that contain Al has not been observed. According to Kim et al [34], the improved corrosion resistance of FeCrAl alloy (Fe-22Cr-5Al-3Mo) and CrAl alloy (Cr-15Al) coatings under normal operating conditions can be attributed to the formation of a stable Cr-rich spinel structure, which suppresses Al diffusion.…”

Section: Development Of Atf Coating Materialsmentioning

confidence: 99%

“…It is worth mentioning that besides the constant attention paid to the research and development of Cr coatings, the Korea Atomic Energy Research Institute (KAERI) of South Korea has creatively proposed the concept of an ATF cladding with a modified surface that integrates Cr or CrAl coatings and an oxide dispersion-strengthened (ODS) surface treatment [6,33,34,69]. The aim was to simultaneously improve high-temperature steam oxidation resistance and high-temperature mechanical properties of Zr alloy claddings.…”

Section: Development Of Atf Coating Materialsmentioning

confidence: 99%

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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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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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Section: Current Status Of Application Of Zirconium Alloy Claddingsmentioning

confidence: 99%

Section: Current Status Of Application Of Zirconium Alloy Claddingsmentioning

confidence: 99%

Section: Proposal and Development Of Atf Claddingmentioning

confidence: 99%

Section: Development Of Atf Coating Materialsmentioning

confidence: 99%

Section: Development Of Atf Coating Materialsmentioning

confidence: 99%

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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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Impacts of an ATF cladding on neutronic performances of the soluble‐boron‐free ATOM core

2020

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Impact Fretting Wear Behavior of Cr-Alloy Coating Layer for Accident-Tolerant Fuel Cladding

Lee

Park

Jung

et al. 2022

The Minerals, Metals &Amp; Materials Series

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Out-of-pile performance of surface-modified Zr cladding for accident tolerant fuel in LWRs

Cited by 66 publications

References 11 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

Impacts of an ATF cladding on neutronic performances of the soluble‐boron‐free ATOM core

Impact Fretting Wear Behavior of Cr-Alloy Coating Layer for Accident-Tolerant Fuel Cladding

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