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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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Post-quench ductility evaluation of Zircaloy-4 and select iron alloys under design basis and extended LOCA conditions

TL;DR: In this paper, the parabolic rate constant for Zircaloy-4 tubing samples at 1200°C was determined to be k ǫ = 2.173 −1.173 × 10 7 −1/cm 4 /s, in excellent agreement with the Cathcart-Pawel correlation.
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Integral LOCA fragmentation test on high-burnup fuel

TL;DR: The Severe Accident Test Station at Oak Ridge National Lab as mentioned in this paper provides various temperature profiles, steam, and thermal shock conditions necessary for integral loss of coolant accident testing, defueled oxidation quench testing, and high-temperature beyond design basis accident testing.
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Oxidation Behaviour of Alloys 800H, 3033 and 304 in High-Temperature Supercritical Water

TL;DR: In this article, alloys 800H, 3003 and 304 were tested in supercritical water-cooled reactors (SCWRs) at 700 ÂC and 25 ÂMPa for 1000 Âh.
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Development of accident tolerant FeCrAl-ODS fuel cladding for BWRs in Japan

TL;DR: In this paper, the authors report on the progress of the development of accident tolerant FeCrAl-ODS fuel claddings for boiling water reactors (BWRs) in Japan.
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In-situ TEM observation of the evolution of dislocation loops and helium bubbles in a pre helium irradiated FeCrAl alloy during annealing

TL;DR: In this article, He+-irradiated TEM samples with a normal chemical composition of Fe-13.2Cr-5.6Al-2Mo-2ZrC (wt.%) were annealed and observed by in-situ transmission electron microscopy.
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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