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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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document
CEA studies on High temperature oxidation and hydriding of Zr based nuclear fuel claddings upon LOCA transients phenomenology, mechanisms and modelling => consequences on mechanical properties
Abstract
During a hypothetical loss-of-coolant accident (LOCA) in a light water reactor, fuel claddings made of zirconium alloys are loaded by internal pressure and exposed to steam at high temperature (HT, potentially up to 1200DC) during a few minutes, before being cooled then water quenched. During such a transient, the cladding material undergoes a number of metallurgical changes. These evolutions have a strong influence on the cladding mechanical properties, which have to remain sufficient for safety reasons. In particular, the cladding is embrittled by its oxidation at HT, due to the growth of an oxide layer, oxygen diffusion through the underlying metal and hydrogen absorption in some conditions. This presentation will provide an overview of the studies carried out at CEA (in collaboration with EDF, AREVA and other laboratories from France and other countries) since the 1990s to (i) understand the phenomenology and the mechanisms of oxidation and hydriding of Zr alloys at HT, (ii) evaluate their consequences on the cladding mechanical properties and (iii) model and simulate the phenomena.The experimental approach relies on HT steam oxidation and water quenching tests performed in dedicated facilities (DEZIROX 1 et 2, CINOG BP et HP with more than 2000 tests performed to date), mechanical testing (ring compression, bending, impact) and multiscale characterization of the material microstructure by using various complementary techniques (microscopy, electron probe micro analysis, micro elastic recoil detection analysis, X-ray and neutron diffraction, neutron radiography/tomography). The modeling work includes the development of a thermodynamic database (Zircobase) and of a multi-component diffusion database (Zircomob), thermodynamic calculations (Thermo-Calc together with the Zircobase database), numerical modeling of HT oxidation (Dictra associated with the Zircomob database, EKINOX-Zr with the Zircobase database), modeling of the material mechanical properties and finite element simulation of mechanical tests. Various Zr alloys have been studied Zircaloy-4, M5, model alloys The influence of several parameters has been investigated pre-transient oxide layer and hydriding resulting from in-service corrosion, oxidation temperature (700-1400DC) and time (1 min up to a few hours), steam pressure (1-80 bar), cladding having burst or not, cooling scenario This work has contributed to a better understanding of oxidation and hydriding of Zr alloys at HT and to the development of rather predictive models. Nevertheless, there are still some pending issues and some of the models still need to be improved to become fully predictive. Thanks to its expertise and to the methodologies, devices, tools and models developed to study the behavior of Zr alloys under LOCA conditions, CEA is contributing for a few years to the development, for light water reactors, of enhanced accident tolerant fuel claddings (Cr-coated Zr based and sandwich SiC-SiC claddings), having in particular a higher resistance to oxidation at HT.