The Experts below are selected from a list of 15282 Experts worldwide ranked by ideXlab platform
Darryl P. Butt - One of the best experts on this subject based on the ideXlab platform.
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Oxidation behavior of Zirconium, Zircaloy-3, Zircaloy-4, Zr-1Nb, and Zr-2.5Nb in air and oxygen
Nuclear Materials and Energy, 2019Co-Authors: Jordan L. Vandegrift, Patrick M. Price, John-paul Stroud, Clemente Parga, Isabella J. Van Rooyen, Brian J. Jaques, Darryl P. ButtAbstract:Abstract The Transient Reactor Test (TREAT) facility at the Idaho National Laboratory currently utilizes a legacy Zircaloy-3 cladding, which is no longer commercially available. TREAT is air cooled and routinely operates at temperatures well above that of traditional reactor designs. This study investigates the oxidation behavior of pure zirconium and its alloys (Zircaloy-3, Zircaloy-4, Zr-1Nb, Zr-2.5Nb) in Ar+20%O2 and N2+20%O2 atmospheres at temperatures ranging from 400–800 °C to determine which alloy should be implemented as TREAT's cladding. While the oxidation behavior of zirconium based cladding materials has been extensively documented, this study focuses on direct comparison between legacy Zircaloy-3 and contemporary alloys using a flat plate geometry and similar conditions seen at the TREAT facility. In this work, thermogravimetric analysis was used to measure both steady state and breakaway oxidation, which was then used to calculate oxidation rate constants and activation energies of each material. Oxide thickness was evaluated through microscopy of oxidized specimen cross sections. The Zircaloy-3 and Zr-1Nb alloys were found to be the most resistant to oxidation under the conditions of this study, whereas the Zr-2.5Nb alloy was found to be the most susceptible.
Jordan L. Vandegrift - One of the best experts on this subject based on the ideXlab platform.
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Oxidation behavior of Zirconium, Zircaloy-3, Zircaloy-4, Zr-1Nb, and Zr-2.5Nb in air and oxygen
Nuclear Materials and Energy, 2019Co-Authors: Jordan L. Vandegrift, Patrick M. Price, John-paul Stroud, Clemente Parga, Isabella J. Van Rooyen, Brian J. Jaques, Darryl P. ButtAbstract:Abstract The Transient Reactor Test (TREAT) facility at the Idaho National Laboratory currently utilizes a legacy Zircaloy-3 cladding, which is no longer commercially available. TREAT is air cooled and routinely operates at temperatures well above that of traditional reactor designs. This study investigates the oxidation behavior of pure zirconium and its alloys (Zircaloy-3, Zircaloy-4, Zr-1Nb, Zr-2.5Nb) in Ar+20%O2 and N2+20%O2 atmospheres at temperatures ranging from 400–800 °C to determine which alloy should be implemented as TREAT's cladding. While the oxidation behavior of zirconium based cladding materials has been extensively documented, this study focuses on direct comparison between legacy Zircaloy-3 and contemporary alloys using a flat plate geometry and similar conditions seen at the TREAT facility. In this work, thermogravimetric analysis was used to measure both steady state and breakaway oxidation, which was then used to calculate oxidation rate constants and activation energies of each material. Oxide thickness was evaluated through microscopy of oxidized specimen cross sections. The Zircaloy-3 and Zr-1Nb alloys were found to be the most resistant to oxidation under the conditions of this study, whereas the Zr-2.5Nb alloy was found to be the most susceptible.
Satoshi Hirano - One of the best experts on this subject based on the ideXlab platform.
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Microstructural studies of friction stir welded Zircaloy-4
Scripta Materialia, 2012Co-Authors: Yutaka S. Sato, Yoshito Nagahama, Sergey Mironov, Hiroyuki Kokawa, Seung Hwan C. Park, Satoshi HiranoAbstract:Friction stir welding was applied to a zirconium alloy, Zircaloy-4, using a Co-based alloy tool. Zircaloy-4 was successfully welded, and a shiny, smooth surface was obtained. FSW produced a defect-free weld with a fine equiaxed grain structure in the stir zone, which caused an increase in hardness.
D. M. Pasquevich - One of the best experts on this subject based on the ideXlab platform.
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Zirconium recovery from Zircaloy shavings
Journal of Materials Science, 1996Co-Authors: Ana E. Bohé, J. J. Andrade Gamboa, E. M. Lopasso, D. M. PasquevichAbstract:A chlorination process for recovering Zr from Zircaloy scrap has been studied. Zircaloy chlorination was possible at temperatures as low as 220 °C. The scale microstructure and its effect on the Zircaloy reactivity was analysed using Thermogravimetric analysis (TGA), X-ray diffraction (XRD), energy dispersive X-ray spectroscopy (EDXS) and scanning electron microscopy (SEM) techniques. A solid-solid phase transformation took place into the oxide scale during the Zircaloy chlorination. Zirconium, as ZrCl4(g), was separated from the oxide scale and chlorides of Cr and Fe. The effect of the reaction temperature was also analysed.
Isabella J. Van Rooyen - One of the best experts on this subject based on the ideXlab platform.
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Oxidation behavior of Zirconium, Zircaloy-3, Zircaloy-4, Zr-1Nb, and Zr-2.5Nb in air and oxygen
Nuclear Materials and Energy, 2019Co-Authors: Jordan L. Vandegrift, Patrick M. Price, John-paul Stroud, Clemente Parga, Isabella J. Van Rooyen, Brian J. Jaques, Darryl P. ButtAbstract:Abstract The Transient Reactor Test (TREAT) facility at the Idaho National Laboratory currently utilizes a legacy Zircaloy-3 cladding, which is no longer commercially available. TREAT is air cooled and routinely operates at temperatures well above that of traditional reactor designs. This study investigates the oxidation behavior of pure zirconium and its alloys (Zircaloy-3, Zircaloy-4, Zr-1Nb, Zr-2.5Nb) in Ar+20%O2 and N2+20%O2 atmospheres at temperatures ranging from 400–800 °C to determine which alloy should be implemented as TREAT's cladding. While the oxidation behavior of zirconium based cladding materials has been extensively documented, this study focuses on direct comparison between legacy Zircaloy-3 and contemporary alloys using a flat plate geometry and similar conditions seen at the TREAT facility. In this work, thermogravimetric analysis was used to measure both steady state and breakaway oxidation, which was then used to calculate oxidation rate constants and activation energies of each material. Oxide thickness was evaluated through microscopy of oxidized specimen cross sections. The Zircaloy-3 and Zr-1Nb alloys were found to be the most resistant to oxidation under the conditions of this study, whereas the Zr-2.5Nb alloy was found to be the most susceptible.
