| People | Locations | Statistics |
|---|---|---|
| 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
ANALYTICAL APPROACH TO MATERIALS CHARACTERISATION IN FUTURE NUCLEAR REACTORS (GENERATION IV)
Abstract
The CEA contributes to the development of the reactors selected under the Generation IV. Thermochemical studies are conducted to investigate the fuel and the cladding used for GFR reactor and the materials used of neutron absorbent in SFR reactor under nominal and accidental conditions (2000°C).For the GFR reactor, the fuel studied is constituted by a mixed uranium-plutonium carbide and the cladding consists of several layers of ceramic materials (SiC) and a metal liner. In order to compile a thermodynamic database on the formation of liquid ternary phases at high temperatures, USiC samples have been prepared with various chemical compositions then heat treated within a range of 1630°C to 1920°C. Other types of samples were also prepared with the same temperature treatment to study the phases formed during the interaction between sheath type steel, B4C and fuel UO2 in SFR reactor.Materials characterization requires the use of a variety of analytical tools (XRD, EBSD, SEM, and EPMA). The measurement of light elements by microanalysis is still complex and must taking into account numerous phenomena :- native oxidation of UC, - spectral interference with U, C, O for carbon measurement,- carbon contamination by the electron beam,- chemical shift for B, C, O.The analytic method was validated on standards before applying it USiC and UBCO samples. The chemical compositions measured were in good agreement with the phases measured by XRD. A study of EBSD texture between sheath type steel, B4C and UO2 was also conducted to better understand the diffusion mechanisms.