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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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Gossé, S.
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (16/16 displayed)
- 2018High temperature corrosion phenomena during a nuclear severe accident - The corium-concrete interaction
- 2018Thermodynamic Assessment of the Fe-Te System. Part I: Experimental studycitations
- 2017Thermodynamic investigation of the Cr-O-U and Cr-O-Zr systems
- 2017Thermodynamic modelling of key metallic sub-systems for the treatment of mid-level wastes
- 2017Thermodynamic modelling of key metallic sub-systems for the treatment of mid-level wastes
- 2017The TAF-ID database Application calculations to severe accidents and irradiated fuel
- 2016Experimental and thermodynamic calculations results on pwr and srf corium subsystems
- 2016Thermodynamic assessment of the PdRhRu system using calphad and first-principles methodscitations
- 2016High temperature experimental contribution to the thermodynamic modeling of corium pools
- 2016High temperature experimental contribution to the thermodynamic modeling of corium pools
- 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
- 2015Modélisation thermodynamique de l'interaction entre le verre et les phases molybdates.
- 2012Mechanism of RuO2 Crystallization in Borosilicate Glass: An Original in Situ ESEM Approachcitations
- 2011Thermodynamic study of the uranium–vanadium systemcitations
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document
Experimental investigation and thermodynamic modelling of the in-vessel corium for severe accident studies in PWR reactors
Abstract
During a severe accident in a PWR reactor, the oxide nuclear fuel (UO2 or MOX) reacts at high temperature with the zirconium alloy clad and the steel vessel to form a partially or fully molten mixture so-calledin-vessel corium . In such a case, the corium forms a pool in the bottom of the vessel, constituted of two liquid phases, metallic and oxide. The formation of such a configuration of the corium pool is due to the existence of a miscibility gap in the liquid state. The fractions and compositions of these liquid phases have to be well known in order to model the thermal hydraulic properties of the pool. The aim of the present work is to investigate experimentally the thermodynamic properties of the U-Zr-O-Fe system representative for the in-vessel corium to improve the thermodynamic modelling using the Calphad method. Laser heating techniques as well as heat treatments are used to measure solid/liquid transition temperatures and to highlight the miscibility gap in the liquid state. Experimental data are used to assess the thermodynamic properties of this key system. Both experimental and theoretical results will be presented.