Journal ArticleDOI
High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments
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TLDR
In this paper, a comparison of a range of commercial and model alloys, conventional austenitic steels do not have sufficient oxidation resistance with only ∼18Cr-10Ni, and higher alloyed type 310 stainless steel is protective but Ni is not a desirable alloy addition for this application.About:
This article is published in Journal of Nuclear Materials.The article was published on 2013-09-01. It has received 356 citations till now. The article focuses on the topics: Alloy & Corrosion.read more
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Accident tolerant fuel cladding development: Promise, status, and challenges
TL;DR: A review of the development status for three accident tolerant fuel cladding technologies, namely coated zirconium-based cladding, ferritic alumina-forming alloy cladding and silicon carbide fiber-reinforced SCCM composite, is offered in this paper.
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Advanced Oxidation Resistant Iron-Based Alloys for LWR Fuel Cladding
TL;DR: In this article, an application of advanced oxidation-resistant iron alloys as light water reactor fuel cladding is proposed, based on specific limitations associated with zirconium alloys.
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Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
TL;DR: In this paper, a set of model FeCrAl alloys containing 10−20Cr, 3−5Al, and 0−0.12Y in weight percent, were prepared by conventional arc-melting and hot-working processes to explore the effect of composition on the properties of FecrAlY alloys.
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
TL;DR: 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.
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Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions
TL;DR: In this paper, the impact of fuel/cladding materials on the fuel performance at normal operating conditions and on the reactor system under DB and BDB accident conditions was analyzed. But the authors focused on the impact on the nuclear power station's fuel performance.
References
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Journal ArticleDOI
Effect of Cr and Ni Contents on the Oxidation Behavior of Ferritic and Austenitic Model Alloys in Air with Water Vapor
R. Peraldi,Bruce A. Pint +1 more
TL;DR: Ferritic and austenitic model alloys with various contents of Cr and Ni ranging between 10−20% and 0−30%, respectively, were oxidized in air + 10% water vapor during 1 hr cyclic oxidation at 650°C and 800°C as discussed by the authors.
Journal ArticleDOI
Oxidation of fuel cladding candidate materials in steam environments at high temperature and pressure
TL;DR: Very low reaction kinetics were observed with alumina-forming FeCrAl alloys at 1200 °C while Fe-Cr alloys with only 15-20% Cr were rapidly attacked as mentioned in this paper.
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The Kinetics of Oxidation of Zircaloy‐4 in Steam at High Temperatures
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The microstructure of the scale formed during the high temperature oxidation of a fecralloy steel
TL;DR: In this paper, the authors used micro-structural properties of Fecralloy steel to characterize the appearance of the protective scales formed on steel exposed to an oxidizing environment at temperatures of 1000, 1100 or 1200°C with the aid of microstructural techniques.
Journal ArticleDOI
Oxidation of Zircaloy by steam
M. Moalem,Donald R. Olander +1 more
TL;DR: In this paper, the oxidation of Zircaloy by steam and by steam-hydrogen mixtures was studied experimentally from 1100-1600°C using the continuously-recording gravimetric method.