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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.
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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.

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Silicon carbide composite for light water reactor fuel assembly applications

TL;DR: The feasibility of using SiC f -SiC m composites in light water reactor (LWR) fuel designs was evaluated in this paper, which was motivated by the desire to improve fuel performance under normal and accident conditions.
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A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys ☆

TL;DR: In this article, small angle neutron scattering techniques were coupled with atom probe tomography to assess the composition and morphology of the resulting α-phase precipitates, and the precipitate morphology evolution with dose exhibited a transient coarsening regime akin to previously observed behavior in aged Fe-Cr alloys.
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Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys

TL;DR: In this paper, the authors focused on the mechanical properties of model FeCrAl alloys and of a commercial Fe-CrAl alloy with up to 13.8 displacements per atom (dpa) at irradiation temperatures between 320 and 382°C.
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Effects of Laves phase particles on recovery and recrystallization behaviors of Nb-containing FeCrAl alloys

TL;DR: The microstructures and mechanical properties of deformed and annealed Nb-containing FeCrAl alloys were investigated in this article, where fine dispersion of Fe2Nb-type Laves phase particles was observed in the bcc-Fe matrix after applying a thermomechanical treatment, especially along grain/subgrain boundaries.
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Dislocation loop evolution during in-situ ion irradiation of model FeCrAl alloys

TL;DR: In this article, the microstructural damage consisted of dislocation loops with ½-111 and 〈100〉 Burgers vectors with a dose of 2.5 displacements per atom (dpa) at 320°C.
References
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Experimental observations in support of the dynamic-segregation theory to explain the reactive-element effect

TL;DR: In this article, a model was developed to explain the effects associated with the addition of reactive elements that is based on the segregation of reactive-element ions to scale grain boundaries and the metal-oxide interface.
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Structural materials challenges for advanced reactor systems

P. Yvon, +1 more
TL;DR: In this paper, the authors give a brief overview of various materials that are essential to establish advanced systems feasibility and performance for in pile and out of pile applications, such as ferritic/martensitic steels (9-12% Cr), nickel based alloys (Haynes 230, Inconel 617, etc.), oxide dispersion strengthened ferritic and martensite steels, and ceramics (SiC, TiC, etc.).
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Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys

TL;DR: In this article, the differences and similarities of different ODS steels are explained in terms of the microstructures of the steels, and observations are explained using the properties of the ODS micro-structures.
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Paralinear Oxidation of CVD SiC in Water Vapor

TL;DR: In this article, the long-term degradation rate of CVD SiC is determined by the volatility of the silica scale, which is observed as the water vapor oxidized the SiC and simultaneously volatilized the scale.
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The Effect of Oxide Volatilization on the Oxidation Kinetics of Cr and Fe‐Cr Alloys

TL;DR: In this paper, the authors derived equations which describe the oxidation behavior of a system in which both diffusive and gas/oxide interface processes occur simultaneously, and applied these equations to the oxidation of Cr and Fe-Cr alloys.
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