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| Naji, M. |
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| Motta, Antonella |
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| Aletan, Dirar |
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| Mohamed, Tarek |
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| Ertürk, Emre |
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| Taccardi, Nicola |
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| Kononenko, Denys |
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| Petrov, R. H. | Madrid |
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| Alshaaer, Mazen | Brussels |
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| Bih, L. |
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| Casati, R. |
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| Muller, Hermance |
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| Kočí, Jan | Prague |
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| Šuljagić, Marija |
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| Kalteremidou, Kalliopi-Artemi | Brussels |
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| Azam, Siraj |
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| Ospanova, Alyiya |
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| Blanpain, Bart |
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| Ali, M. A. |
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| Popa, V. |
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| Rančić, M. |
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| Ollier, Nadège |
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| Azevedo, Nuno Monteiro |
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| Landes, Michael |
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| Rignanese, Gian-Marco |
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Saux, Matthieu Le
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (21/21 displayed)
- 2021DLI-MOCVD Crx Cy coating to prevent Zr-based cladding from inner oxidation and secondary hydriding upon LOCA conditionscitations
- 2021Combined effects of temperature and of high hydrogen and oxygen contents on the mechanical behavior of a zirconium alloy upon cooling from the βZr phase temperature rangecitations
- 2020High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and processcitations
- 2020Phase transformations during cooling from the βZr phase temperature domain in several hydrogen-enriched zirconium alloys studied by in situ and ex situ neutron diffractioncitations
- 2020Breakaway oxidation of zirconium alloys exposed to steam around 1000 °Ccitations
- 2020A model to describe the cyclic anisotropic mechanical behavior of short fiber-reinforced thermoplasticscitations
- 2020Fatigue criteria for short fiber-reinforced thermoplastic validated over various fiber orientations, load ratios and environmental conditionscitations
- 2019Comportement mécanique d'un revêtement de chrome déposé sur un substrat en alliage de zirconium
- 2019In-situ time-resolved study of structural evolutions in a zirconium alloy during high temperature oxidation and coolingcitations
- 2019Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactorscitations
- 2019A model to describe the cyclic anisotropic mechanical behavior of short fiber-reinforced thermoplastics
- 2018High-temperature oxidation resistance of chromium-based coatings deposited by DLI-MOCVD for enhanced protection of the inner surface of long tubescitations
- 2017Secondary hydriding of zirconium-based fuel claddings at high temperature (LOCA conditions). Part 2: Effect of high hydrogen contents on metallurgical and mechanical properties. Part 1: Multi-scale study of hydrogen distribution
- 2017Study of secondary hydriding at high temperature in zirconium based nuclear fuel cladding tubes by coupling information from neutron radiography/tomography, electron probe micro analysis, micro elastic recoil detection analysis and laser induced breakdown spectroscopy microprobecitations
- 2016Out-of-pile RandD on chromium coated nuclear fuel zirconium based claddings for enhanced accident tolerance in LWRs
- 2016CEA studies on High temperature oxidation and hydriding of Zr based nuclear fuel claddings upon LOCA transients phenomenology, mechanisms and modelling => consequences on mechanical properties
- 2016Mechanical behavior at high temperature of highly oxygen- or hydrogen-enriched α and (prior-) $beta$ phases of zirconium alloys
- 2016Mechanical behavior at high temperatures of highly oxygen- or hydrogen-enriched α and (Prior-) β phases of zirconium alloyscitations
- 2015In-situ X-ray diffraction analysis of zirconia layer formed on zirconium alloys oxidized at high temperaturecitations
- 2010Behavior and failure of uniformly hydrided Zircaloy-4 fuel claddings between 25 °C and 480 °C under various stress states, including RIA loading conditionscitations
- 2008A model to describe the anisotropic viscoplastic mechanical behavior of fresh and irradiated Zircaloy-4 fuel claddings under RIA loading conditionscitations
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article
In-situ X-ray diffraction analysis of zirconia layer formed on zirconium alloys oxidized at high temperature
Abstract
In the case of a hypothetical loss of primary coolant accident (LOCA) in a light water reactor, the zirconium alloys fuel cladding would be oxidized in steam at high temperature, typically in the range 800–1200 °C. The monoclinic to tetragonal phase martensitic transition of zirconia occurs within this temperature range and complex phenomena possibly having an impact on the oxidation kinetics are then to be expected. In order to provide an accurate description of the structure and microstructure of the oxide layers, systematic X-ray diffraction analyses have been performed in-situ under oxidizing atmosphere at high temperature (between 800 and 1100 °C) on Zircaloy-4 and M5™ sheet samples. It was confirmed that the volume fraction of the tetragonal and monoclinic zirconia phases formed during oxide growth drastically depends on the oxidation temperature. For example, the few outer microns of the oxide are fully tetragonal above 1050 °C and contain only 20% of tetragonal phase at 800 °C. It was also shown that cooling after oxidation induces irreversible phase transitions within the oxide. As a consequence, both the structure and the microstructure of the growing oxide cannot be observed post-facto, neither at room temperature nor after reheating at the prior oxidation temperature. It has been deduced from microstructural analyses that the grain size of the tetragonal zirconia phase is nanometric, about 100 nm during oxidation at 1100 °C down to 20 nm after cooling down to room temperature. This small grain size allows the stabilization of the tetragonal phase. The lattice parameters of the monoclinic and tetragonal zirconia phases have been analyzed, during both high temperature oxidation and cooling. In both cases, it appears the ‘a’ and ‘b’ cell parameters of the monoclinic phase are strongly constrained by the tetragonal ‘a’ one. The structural characteristics of the oxide formed at high temperature on Zircaloy-4 and M5™ are quite similar. All those results can be interpreted in the frame of the classical description of the monoclinic–tetragonal martensitic transition of zirconia.