| 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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Brackx, Emmanuelle
CEA Marcoule
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (18/18 displayed)
- 2023Corium materials characterizations through electron microscopy and X-ray diffraction
- 2023Study of the Crystallization in a Glass-Ceramic Sealcitations
- 2023Study of the Crystallization in a Glass-Ceramic Sealcitations
- 2022CORIUM MATERIAL ANALYSIS BY EPMA AND DIFFRACTIONS METHODS
- 2021Chemical interaction between uranium dioxide, boron carbide and stainless steel at 1900 °C — Application to a severe accident scenario in sodium cooled fast reactorscitations
- 2019ANALYTICAL APPROACH TO MATERIALS CHARACTERISATION IN FUTURE NUCLEAR REACTORS (GENERATION IV)
- 2018Study of prototypical corium UZrO from quenching, by a multi-scale approach
- 2017Thermodynamic investigation of the Cr-O-U and Cr-O-Zr systems
- 2017molybdenum behaviour during u-al research reactor spent fuel dissolution
- 2017Quantification of hypo eutectic b-c-fe-o under severe accident condition in nuclear material by epma
- 2016Compaction of porous metal oxide microspheres a multi-scale approach
- 2016Experimental contribution to the corium thermodynamic modelling – The U–Zr–Al–Ca–Si–O systemcitations
- 2016quantification by epma of glass for nuclear application
- 2015Experimental investigation and thermodynamic modelling of the in-vessel corium for severe accident studies in PWR reactors
- 2015Experimental investigation and thermodynamic modelling of the in-vessel corium for severe accident studies in PWR reactors
- 2015Experimental study and thermodynamic modelling of corium mixtures Application to severe accidents in Pressurized Water Reactors
- 2013Analytical approach to usic measurement by electron probe microanalysis
- 2011Quantification of boron by epma in nuclear glass
Places of action
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conferencepaper
Experimental study and thermodynamic modelling of corium mixtures Application to severe accidents in Pressurized Water Reactors
Abstract
International audience ; During a severe accident in a nuclear reactor, extreme temperatures may be reached (T > 2500 K). In these conditions, the nuclear fuel may react with the Zircaloy cladding and then with the steel vessel, forming a mixture of solid-liquid phases called in-vessel corium. In the worst scenario, this mixture may pierce the vessel and reach the concrete underneath the reactor. In the framework of the development of the TAF-ID thermodynamic database (www.oecd-nea.org/science/taf-id) on nuclear fuel and to predict the high temperature behaviour of the corium+concrete system, new high temperature thermodynamic data are needed. The LM2T at CEA Saclay centre started an experimental campaign of measure of phase equilibria at high temperature (up to 2400 K) on interesting corium sub-systems. Furthermore a new laser heating setup has been conceived. This technique allows very high temperature measures (T>3000 K) limiting the interactions between the sample and the surroundings. New phase equilibria data on the U-Zr-O system and on the U-Zr-Al-Ca-Si-O system will be presented. Moreover original melting temperature data on the PuO2-UO2-ZrO2 system obtained in collaboration with the JRC-ITU, will be also shown.