| 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
DLI-MOCVD Crx Cy coating to prevent Zr-based cladding from inner oxidation and secondary hydriding upon LOCA conditions
Abstract
Zirconium-based claddings with an outer chromium coating resistant to corrosion are studied and devel- oped as an evolutionary Enhanced Accident Tolerant Fuel (E-ATF) concept for light water reactors. How- ever, in hypothetical LOss-of-Coolant-Accident (LOCA) conditions, following clad ballooning and burst, the outer coating does not allow to protect the inner surface of the cladding from High Temperature (HT) steam oxidation and associated secondary hydriding due to steam starvation occurring within the gap between the clad inner surface and the nuclear fuel pellets. To address this issue, DLI-MOCVD (Direct Liquid Injection of Metal-Organic precursors - Chemical Vapor Deposition) Cr x C y coatings have been developed and successfully deposited onto the inner surface of Zr- based cladding tube prototypes. Then, preliminary two-sided oxidation tests have shown that such inner coating is able to increase the resistance to oxidation at HT of the inner clad surface. The present study aimed at performing new steam oxidation tests at 1200 °C on Zircaloy-4 clad proto- types with a 5–20μm-thick Cr x C y inner coating, in conditions more representative of LOCA, after a first internal pressure-induced burst step. Additionally, complementary two-sided steam oxidation tests have been carried out up to 1 h at 1200 °C, on short inner and/or outer-coated clad segments. Finally, Post- Quench (PQ) Ring Compression Tests (RCTs), fractographic analysis and deep metallurgical investigations including neutron-tomography have been performed to get more insights into the PQ behavior of the inner-coated clad. Among other results, it is shown that the inner Cr x C y coating makes it possible to reduce significantly the oxidation and the associated secondary hydriding of the clad inner surface, after ballooning and burst. After at least 600 s under steam at 1200 °C, the reference uncoated clad fails upon final water quenching while the inner-coated prototype keeps its integrity. PQ RCTs showed a higher strength of the inner- coated material, related to lower oxygen and hydrogen uptakes of the substrate.