| 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
molybdenum behaviour during u-al research reactor spent fuel dissolution
Abstract
International audience ; In the frame of Research Reactors Spent Fuel (RRSF) treatment by hydrometallurgy, the dissolution in nitric acid of irradiated U-Al, is a key issue because of the low solubility of molybdenum fission product in presence of high concentration of aluminium. In this study, the values of molybdenum solubility have been accurately measured in different operating conditions. Studies have carried out with non-active materials. To be more representative of metallic fuel, uranium-molybdenum alloy powder and molybdenum metal have been dissolved in aluminium nitrate solutions at high temperature. In order to be sure that molybdenum solubility has been reached, experiments have been carried out with an excess of molybdenum metal. In spite of this excess addition, metallic elements have been dissolved completely after stirring time of thirty minutes with a magnetic stirrer. Shortly after this total dissolution, a slow molybdenum precipitation has been observed for almost 15 hours. An experimental protocol has been developed to properly wash precipitates in order to determine their elemental composition. No uranium has been detected in the washed precipitate by ICP-AES measurements performed after redissolution of solids in aluminium free nitric acid solutions. Further analyses by Scanning Electron Microscope have shown a needle-like morphology. Energy-dispersive X-ray spectroscopy analyses on several selected areas have confirmed the absence of uranium in precipitates. EDX semi-quantification has been carried out on ionically polished particles. They are composed of 75% oxygen and 25% molybdenum, suggesting MoO3 compounds. X-ray diffraction spectra of powders have confirmed this result all samples matched the crystallographic form of MoO3.