Study of Oxidation Kinetics in Air of Zircaloy-4 by <i>in Situ</i> X-Ray Diffraction

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Advances in Materials Physics and Chemistry

ISSN Print: 2162-531X
ISSN Online: 2162-5328
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"Study of Oxidation Kinetics in Air of Zircaloy-4 by in Situ X-Ray Diffraction"
written by Noureddine Selmi, Ali Sari,
published by Advances in Materials Physics and Chemistry, Vol.3 No.2, 2013

has been cited by the following article(s):

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[7]	Thermophysical properties of molten Zr1− xOx (x= 0.1, 0.2) measured by electrostatic levitation
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[14]	X-Ray Computer Tomography Study of Degradation of the Zircaloy-2 Tubes Oxidized at High Temperatures
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[20]	Characterization of Nuclear Fuel Rod Cladding Zirconium Alloys
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[21]	Thermal processing of ZR-1% NB tube in oxygenand nitrogen containing gaseous mediums
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[23]	Oxidation and nitriding tubes of Zr-1% Nb zirconium alloy
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[24]	Effect of applied current on the formation of defect in PWR nuclear fuel rods in resistance pressure welding process
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[1]	Systematics of zircaloy-4 lattice parameters from 2 K to PWR irradiation conditions The European Physical Journal Plus, 2024 DOI:10.1140/epjp/s13360-024-05589-y

[2]	Mechanism of wear in zircaloy-4 under different loading conditions Tribology International, 2023 DOI:10.1016/j.triboint.2023.108369

[3]	DFT calculations of solute-vacancy binding in Zirconium-based Zr–Nb–Sn alloy Nuclear Materials and Energy, 2022 DOI:10.1016/j.nme.2022.101221

[4]	DFT calculations of solute-vacancy binding in Zirconium-based Zr–Nb–Sn alloy Nuclear Materials and Energy, 2022 DOI:10.1016/j.nme.2022.101221

[5]	Effect of Heat Treatment in Oxygen-Containing Medium on Fatigue Life of Zirconium Alloy Strojnícky časopis - Journal of Mechanical Engineering, 2022 DOI:10.2478/scjme-2022-0030

[6]	Effect of Heat Treatment in Oxygen-Containing Medium on Fatigue Life of Zirconium Alloy Strojnícky časopis - Journal of Mechanical Engineering, 2022 DOI:10.2478/scjme-2022-0030

[7]	DFT calculations of solute-vacancy binding in Zirconium-based Zr–Nb–Sn alloy Nuclear Materials and Energy, 2022 DOI:10.1016/j.nme.2022.101221

[8]	DFT calculations of solute-vacancy binding in Zirconium-based Zr–Nb–Sn alloy Nuclear Materials and Energy, 2022 DOI:10.1016/j.nme.2022.101221

[9]	Effect of Heat Treatment in Oxygen-Containing Medium on Fatigue Life of Zirconium Alloy Strojnícky časopis - Journal of Mechanical Engineering, 2022 DOI:10.2478/scjme-2022-0030

[10]	Effect of Heat Treatment in Oxygen-Containing Medium on Fatigue Life of Zirconium Alloy Strojnícky časopis - Journal of Mechanical Engineering, 2022 DOI:10.2478/scjme-2022-0030

[11]	Thermophysical properties of molten Zr1−O (x=0.1, 0.2) measured by electrostatic levitation Journal of Nuclear Materials, 2020 DOI:10.1016/j.jnucmat.2019.151873

[12]	Hydrogen Embrittlement and Oxide Layer Effect in the Cathodically Charged Zircaloy-2 Materials, 2020 DOI:10.3390/ma13081913

[13]	Hydrogen Embrittlement and Oxide Layer Effect in the Cathodically Charged Zircaloy-2 Materials, 2020 DOI:10.3390/ma13081913

[14]	X-Ray Computer Tomography Study of Degradation of the Zircaloy-2 Tubes Oxidized at High Temperatures Advances in Materials Science, 2019 DOI:10.2478/adms-2019-0011

[15]	X-Ray Computer Tomography Study of Degradation of the Zircaloy-2 Tubes Oxidized at High Temperatures Advances in Materials Science, 2019 DOI:10.2478/adms-2019-0011

[16]	Influence of High Temperature Oxidation on Hydrogen Absorption and Degradation of Zircaloy-2 and Zr 700 Alloys High Temperature Materials and Processes, 2019 DOI:10.1515/htmp-2017-0074

[17]	Influence of Heat Treatment in Gas Mediums on Mechanical Properties of Samples of Zr–1%Nb Alloy METALLOFIZIKA I NOVEISHIE TEKHNOLOGII, 2019 DOI:10.15407/mfint.41.02.0227

[18]	Weldability of a zirconium alloy comparing resistance and pulsed laser methods Nuclear Materials and Energy, 2019 DOI:10.1016/j.nme.2019.100693

[19]	X-Ray Computer Tomography Study of Degradation of the Zircaloy-2 Tubes Oxidized at High Temperatures Advances in Materials Science, 2019 DOI:10.2478/adms-2019-0011

[20]	X-Ray Computer Tomography Study of Degradation of the Zircaloy-2 Tubes Oxidized at High Temperatures Advances in Materials Science, 2019 DOI:10.2478/adms-2019-0011

[21]	X-Ray Computer Tomography Study of Degradation of the Zircaloy-2 Tubes Oxidized at High Temperatures Advances in Materials Science, 2019 DOI:10.2478/adms-2019-0011

[22]	X-Ray Computer Tomography Study of Degradation of the Zircaloy-2 Tubes Oxidized at High Temperatures Advances in Materials Science, 2019 DOI:10.2478/adms-2019-0011

[23]	X-Ray Computer Tomography Study of Degradation of the Zircaloy-2 Tubes Oxidized at High Temperatures Advances in Materials Science, 2019 DOI:10.2478/adms-2019-0011

[24]	Hydrogen degradation of pre-oxidized zirconium alloys Advances in Materials Science, 2017 DOI:10.1515/adms-2017-0001

[25]	Effect of applied current on the formation of defect in PWR nuclear fuel rods in resistance pressure welding process Journal of Nuclear Science and Technology, 2015 DOI:10.1080/00223131.2014.971900

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