| People | Locations | Statistics |
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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
Combined 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 range
Abstract
During hypothetical loss-of-coolant accidents (LOCA), zirconium-based nuclear fuel claddings can be exposed to high temperatures in the βZr phase domain and absorb substantial amounts of hydrogen (up to about 3000 weight ppm) and oxygen (up to about 1 weight %). This paper provides novel data about the combined effects of high hydrogen and oxygen contents on the mechanical behavior of the (prior-)βZr phase, as a function of temperature, upon cooling from the βZr phase temperature range. A protocol was developed to homogeneously charge Zircaloy-4 cladding tubes at different hydrogen contents, up to 3200 weight ppm, and oxygen contents, between 0.13 and 0.9 weight %. Tensile tests were then performed at various temperatures between 700 and 30°C upon cooling from the βZr domain. The results show that the mechanical behavior strongly depends on the testing temperature and the hydrogen and oxygen contents. Relationships are proposed to describe the macroscopic ductile-to-brittle transition and the mechanical behavior of the material as a function of temperature, hydrogen and oxygen contents. The predictions based on these relationships are compared to selected data from the literature obtained on claddings oxidized at high temperature, including results from semi-integral LOCA tests. Also, it is shown that considering the combined effects of hydrogen and oxygen is necessary to interpret the mechanical behavior of the material, in particular the embrittlement of claddings subjected to LOCA-relevant secondary hydriding.