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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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Barrachin, Marc
Institut de Radioprotection et de Sûreté Nucléaire
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (17/17 displayed)
- 2024Revisiting the thermodynamic properties of the ZrCr2 Laves phases by combined approach using experimental and simulation methodscitations
- 2021Hafnium Oxidation at High Temperature in Steamcitations
- 2019Critical evaluation of experimental data of solution enthalpy of zirconium in liquid aluminumcitations
- 2019Interrupted heating DTA for liquidus temperature determination of Ag–Cd–In alloyscitations
- 2019Hafnium Oxidation in steam at high Temperature
- 2016Core melt composition at Fukushima Daiichi Results of transient simulations with ASTECcitations
- 2014Fuel and fission product behaviour in early phases of a severe accident. Part II Interpretation of the experimental results of the PHEBUS FPT2 testcitations
- 2014Oxidation effect on steel corrosion and thermal loads during corium melt in-vessel retentioncitations
- 2014Fuel and fission product behaviour in early phases of a severe accident. Part I Experimental results of the PHEBUS FPT2 testcitations
- 2013Late phase fuel degradation in the Phébus FP testscitations
- 2013Early phase fuel degradation in Phébus FP: Initiating phenomena of degradation in fuel bundle testscitations
- 2011Ternary eutectics in the systems FeO-UO2-ZrO2 and Fe2O3-U3O8-ZrO2citations
- 2011First-principles study of defect behavior in irradiated uranium monocarbidecitations
- 2007Phase diagram of the UO2-FeO1+x systemcitations
- 2007Progress in nuclear thermodynamic databanking for MCCI applications
- 2006Phase relations in the ZrO2-FeO systemcitations
- 2006Phase diagram of the ZrO2-FeO systemcitations
Places of action
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document
Progress in nuclear thermodynamic databanking for MCCI applications
Abstract
Thermochemical approach involving modelling and critical assessed thermodynamic data of the corium-concrete chemical system plays an increasing role in order to simulate the ex-vessel corium behaviour during a severe accident. For more than 10 years, a special effort to produce a specific thermodynamic database for nuclear applications (NUCLEA) was made with the support of different organisations in Europe. The CALPHAD method was used to create such a database. For the modelling of the thermochemistry of corium-concrete melts, this method consists in the mathematical description of Gibbs energy of each phase of the U-O-Zr-Fe-Si-Ca-Mg-Al-O complex system, based on a phenomenological model in such a way that the model parameters are adjusted to allow to reproduce the available experimental information. Up to now, for this modelling, the set of thermodynamic data was mainly based on the optimisation of the key quaternary system U-O-Zr-Fe, of the binary oxide systems containing UO2 and/or ZrO2 and concrete oxides and of the ternary CaO-Al2O3-SiO2 oxide system. The Fe-FeO binary is an important system during the oxidation phase of the structural materials and may play a significant role in fixing the oxygen potential of the melts due to large amount of steel available and/or due to the presence of iron oxide in some core catcher concepts of the new generation PWR reactor. Some studies have shown that interaction of melts with iron oxides could not be treated in a simplified approach. For that reason, new modelling of some ternary phase diagrams including iron oxides have been recently undertaken and are presented here with some comparisons with experimental data coming from the voluminous literature on the thermodynamic properties of iron-silicate slags. From this new modelling, the estimations of the liquidus and solidus temperatures of corium-concrete melts can be performed with more accuracy. NUCLEA calculations are compared to the experimental information available on the thermochemistry of corium-concrete melts.