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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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Dacheux, Nicolas
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (17/17 displayed)
- 2024Speciation and chemical behavior of molybdenum in uranium dioxide samples prepared by hydroxide precipitationcitations
- 2024Speciation and chemical behavior of molybdenum in uranium dioxide samples prepared by hydroxide precipitationcitations
- 2023Synthesis and sintering of homogenous Hf1-xMIIIxO2-x/2 ceramics as solid electrolytes for oxygen sensors in liquid sodium
- 2023Understanding the solid/liquid interface evolution during the dissolution of Nd-doped UO2 by macro-/microscopic dual approachcitations
- 2022Synchrotron study of the relations between sintering conditions, structure and cation speciation in (U,Ce)O2+δ ceramics
- 2022Synthesis and sintering of homogenous Hf1-xMIIIxO2-x/2 ceramics as solid electrolytes for oxygen sensors operating in liquid sodium
- 2022Experimental approach to study the alteration of MOX MIMAS fuels in an underwater storage situation
- 2022Characterization and dissolution of (Ru, Rh, Pd, Mo)-bearing (U,Th)O2 heterogeneous mixed oxides for spent fuel modeling
- 2022Impact of impurities on the fabrication and performances of yttrium-doped thoria electrolyte ceramicscitations
- 2021The Role of Water and Hydroxyl Groups in the Structures of Stetindite and Coffinite, MSiO4 (M = Ce, U).citations
- 2020An in-situ electron microscopy study of dual ion-beam irradiated xenotime-type ErPO$_4$citations
- 2019Deciphering the Crystal Structure of a Scarce 1D Polymeric Thorium Peroxo Sulfate
- 2019Impact of the cationic homogeneity on Th0.5U0.5O2 densification and chemical durabilitycitations
- 2019Impact of the cationic homogeneity on Th$_{0.5}$U$_{0.5}$O$_2$ densification and chemical durabilitycitations
- 2017Synthesis and Direct Sintering of Nanosized (M IV ,M III )O 2‐ x Hydrated Oxides as Electrolyte Ceramicscitations
- 2017Study of the hydrothermal synthesis of ThSiO4, USiO4 and CeSiO4 aiming at determining the conditions of PuSiO4 formation
- 2017Novel approaches for the in situ study of the sintering of nuclear oxide fuel materials and their surrogatescitations
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article
Speciation and chemical behavior of molybdenum in uranium dioxide samples prepared by hydroxide precipitation
Abstract
This work aims to investigate the behavior of Mo in UO2±x for being an abundant fission product with a high fission yield and a complex speciation linked to its interaction with the fuel and other fission product elements. UO2-based model compounds containing different Mo contents (between 0 and 15 mol%) were synthesized by a wet-chemistry route using hydroxide precipitation. The recovered powders were converted to oxides, pelletized, and sintered to obtain densified pellets of UO2 incorporating Mo. PXRD analyses and Rietveld refinement calculations indicate that Mo has an almost negligible solubility in the fluorite structures of both UO2 and UO2+x samples. SEM, TEM, and EDX characterizations of the produced UO2 + Mo pellets revealed the homogeneous distribution of nanosized metallic Mo particles of spherical geometry inside and outside the UO2 grains and throughout the whole sample pellets, whatever the amount of Mo added, thus confirming that the solubility of Mo in the fluorite structure is way below 0.6 mol% Mo in accordance with the PXRD results. The microstructural properties of the UO2 + Mo pellets, including density, porosity, Mo particle sizedistribution, and UO2 grain size variation with Mo content, were also determined. The addition of Mo to UO2 reduced the UO2 grain size as compared to UO2 grains in pure pellets, and Mo thus plays an inhibiting role in the UO2 grain growth during sintering. The produced UO2 + Mo pellets exhibit a microstructure similar to that of the real spent nuclear fuel, except that the UO2 grains are smaller. The Mo metallic nanoparticles in these simplified UO2-based model compounds of controlled microstructure could be harnessed as surrogates of the Mo-rich ε-phase metallic nanoparticles in the real spent nuclear fuel for future studies.