Journal ArticleDOI
Current status of materials development of nuclear fuel cladding tubes for light water reactors
Zhengang Duan,Huilong Yang,Yuhki Satoh,Kenta Murakami,Sho Kano,Zishou Zhao,Jingjie Shen,Hiroaki Abe +7 more
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TLDR
In this paper, the impact of alloying elements on the material properties of Zirconium-based claddings has been systematically presented, including the impact on coating layer on the surface of Zr-based alloys, mainly referring coating materials and fabrication methods.About:
This article is published in Nuclear Engineering and Design.The article was published on 2017-05-01. It has received 214 citations till now. The article focuses on the topics: Nuclear fuel.read more
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A review of recent work on discharge characteristics during plasma electrolytic oxidation of various metals
T.W. Clyne,S.C. Troughton +1 more
TL;DR: In this paper, a review describes recent progress on understanding and quantification of the various phenomena that take place during plasma electrolytic oxidation, which is in increasing industrial use for pro...
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Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors
Jean-Christophe Brachet,Isabel Idarraga-Trujillo,Marion Le Flem,Matthieu Le Saux,Valérie Vandenberghe,Valérie Vandenberghe,Stéphane Urvoy,Elodie Rouesne,T. Guilbert,Caroline Toffolon-Masclet,Marc Tupin,Christian Phalippou,Fernando Lomello,Frédéric Schuster,Alain Billard,Gihan Velisa,Cédric Ducros,Frédéric Sanchette +17 more
TL;DR: In this article, the first generation of chromium-based coatings exhibited the most promising behavior: good compromise between oxidation resistance and adhesion to the metallic substrate, good fretting resistance and improved resistance to oxidation in steam at high temperature.
Journal ArticleDOI
High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process
Jean-Christophe Brachet,Elodie Rouesne,J. Ribis,T. Guilbert,Stéphane Urvoy,Guillaume Nony,Caroline Toffolon-Masclet,Matthieu Le Saux,Matthieu Le Saux,Nihed Chaabane,Hervé Palancher,Amandine David,J. Bischoff,Julien Augereau,Edouard Pouillier +14 more
TL;DR: In this paper, the authors studied the oxidation of chromium-coated zirconium-based alloys under steam at temperatures ranging from 800°C up to 1500°C and for oxidation times ranging from a few minutes up to a few hours.
Journal ArticleDOI
Oxidation kinetics of Cr-coated zirconium alloy: Effect of coating thickness and microstructure
TL;DR: In this paper, columnar microstructure was used to prevent alloy oxidation as long as the Cr layer is intact, and a higher activation energy was observed for the dense 4.5μm-thick coating while thicker columnar coatings have 177−183kJ/mol.
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Response of Cr and Cr-Al coatings on Zircaloy-2 to high temperature steam
TL;DR: In this paper, the oxidation behavior of chromium (Cr) and chromium-aluminum (CrAl) coatings with various compositions deposited on Zircaloy-2 to 700°C high-temperature steam (HTS) exposure has been investigated.
References
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Handbook of SiC properties for fuel performance modeling
TL;DR: In this paper, a compilation of non-irradiated and irradiated properties of SiC are provided and reviewed and analyzed in terms of application to TRISO fuels, specifically in the high-temperature irradiation regime.
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The Mn+1AXn phases: Materials science and thin-film processing
TL;DR: A critical review of the M(n + 1)AX(n) phases from a materials science perspective is given in this article, where the authors discuss the potential for low-temperature synthesis, which is essential for deposition of MAX phases onto technologically important substrates.
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Accident tolerant fuels for LWRs: A perspective
Steven J. Zinkle,Steven J. Zinkle,Kurt A. Terrani,Jess C. Gehin,Larry J. Ott,Lance Lewis Snead +5 more
TL;DR: In this article, three general strategies for accident tolerant fuels are explored: modification of current state-of-the-art zirconium alloy cladding to further improve oxidation resistance (including use of coatings), replacement of Zr Alloy cladding with an alternative oxidation resistant high-performance cladding, and replacement of the monolithic ceramic oxide fuel with alternative fuel forms.
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Structural materials for Gen-IV nuclear reactors: Challenges and opportunities
TL;DR: This paper presents a summary of various Gen-IV reactor concepts, with emphasis on the structural materials issues depending on the specific application areas, and demonstrates that novel alloy and microstructural design approaches coupled with new materials processing and fabrication techniques may mitigate the challenges.
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Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys
TL;DR: In this paper, the authors focus on those studies that have resulted in changed views of the importance of various mechanisms of corrosion in water-cooled PWRs and present a review of these studies.