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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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Quaini, Andrea
CEA Saclay
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (9/9 displayed)
- 2023Phase equilibria and solubility limits in the B-Ce-Fe-Nd system
- 2023Phase equilibria and solubility limits in the B-Ce-Fe-Nd system
- 2021Extension to severe accident investigations: Investigation of MOX/steel interaction
- 2021TAF-ID: an international thermodynamic database for nuclear fuels applicationscitations
- 2021Chemical interaction between uranium dioxide, boron carbide and stainless steel at 1900 °C — Application to a severe accident scenario in sodium cooled fast reactorscitations
- 2020Thermodynamic and thermophysical properties of Cu-Si liquid alloyscitations
- 2019ANALYTICAL APPROACH TO MATERIALS CHARACTERISATION IN FUTURE NUCLEAR REACTORS (GENERATION IV)
- 2016Experimental contribution to the corium thermodynamic modelling – The U–Zr–Al–Ca–Si–O systemcitations
- 2015Thermodynamic study of the in-vessel corium - Application to the corium/concrete interaction ; Étude thermodynamique du corium en cuve - Application à l'interaction corium/béton
Places of action
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article
TAF-ID: an international thermodynamic database for nuclear fuels applications
Abstract
The Thermodynamics of Advanced Fuels International Database (TAF-ID) was developed using the Calphad method to provide a computational tool to perform thermodynamic calculations on nuclear fuel materials under normal and off-normal conditions. Different kinds of fuels are considered: oxide, metallic, carbide and nitride fuels. Many fission products are introduced as well as structural materials (zirconium, steel, concrete, SiC) and B4C as absorber, in order to investigate the thermochemistry of irradiated fuels and to predict their chemical interaction with the surrounding materials. The approach to develop the database and the models implemented in the database are described. Examples of models for key ternary systems are presented as well as a few examples on how this tool can be used for different kinds of applications related to the nuclear fuel behavior.