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

TL;DR: In this paper, a comprehensive review of the latest progress in the development of Cr-based surface coatings based on zirconium alloys is presented, which can improve the safety of fuel elements.
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The development of cladding materials for the accident tolerant fuel system from the Materials Genome Initiative

TL;DR: In this article, the design of materials based on the Materials Genome Initiative (MGI) is introduced as the effective scheme in accelerating the development for ATF claddings, and potential technical routes are provided and some examples of preliminary modelling studies as the preparation steps for MGI are presented.
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Quenching of candidate materials for accident tolerant fuel-cladding in LWRs

TL;DR: In this paper, a quenching experiment with a vertical rod was conducted under atmospheric pressure and saturation temperature of water to investigate the boiling parameters in the post-critical heat flux (CHF) regime for the candidate materials of accident tolerant fuel-cladding (ATF): FeCrAl(APMT) and SiC-CVD, compared to commercial cladding material Zircaloy-4(Zry-4) in light water reactors (LWRs).
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Impact toughness of commercial and model FeCrAl alloys

TL;DR: In this paper, the cracking resistance of FeCrAl alloys was evaluated using half-size Charpy impact tests at temperatures ranging from room temperature to 600 °C, and the as-received APMT alloys exhibited poor impact toughness even at 600°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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