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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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Schuller, Sophie
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (39/39 displayed)
- 2023Modelisation of liquid nuclear waste vitrification : focus on the chemical processes
- 2023Rheology of a sodium‐molybdenum borosilicate melt undergoing phase separationcitations
- 2023Liquid-liquid phase separation in borosilicate glass enriched in MoO3 – experimental investigations and thermodynamic calculationscitations
- 2023Observation of glass synthesis by in-situ high temperature ESEM
- 2023Modeling phase separation in the melt
- 2022Spontaneously crystallizing glass-ceramic mechanisms
- 2022Liquid-liquid phase separation in borosilicate glass enriched in MoO3 experimental investigations and thermodynamic calculationscitations
- 2022Characterization and modeling of chemical reactions taking place during the vitrification of high level waste in cold cruciblecitations
- 2022Vitrification of wastes: from unwanted to controlled crystallization, a reviewcitations
- 2022Glass melting and phase separation: Modeling and simulation approaches
- 2021Characterization of immiscibility in calcium borosilicates used for the immobilization of Mo 6+ under Au‐irradiationcitations
- 2021Vitrification of wastes: from unwanted to controlled crystallization, a reviewcitations
- 2021Phase separation and crystallization mechanisms in nuclear glasses
- 2021An integrated thermodynamic approach for phase separation and crystallization in nuclear glasses
- 2021Aqueous alteration of silicate glass: state of knowledge and perspectivescitations
- 2020Mechanism of powellite crystallite expansion within nano-phase separated amorphous matrices under Au-irradiation.
- 2020Nuclear energy and waste vitrification
- 2020Mechanism of powellite crystallite expansion within nano-phase separated amorphous matrices under Au-irradiationcitations
- 2020Characterisation of immiscibility in calcium borosilicates used for the immobilisation of Mo 6+ under Au‐irradiationcitations
- 2020Thermodynamic Modelling of the Pd-Ru-Te-O for Nuclear High-Level Waste Immobilization
- 2019Swift heavy ion-irradiated multi-phase calcium borosilicates: implications to molybdenum incorporation, microstructure, and network topologycitations
- 2018Discovery of a maximum damage structure for Xe-irradiated borosilicate glass ceramics containing powellitecitations
- 2017Impacts of composition and beta irradiation on phase separation in multiphase amorphous calcium borosilicatescitations
- 2017Radionuclides containment in nuclear glasses: an overviewcitations
- 2017Influence of impregnation parameters on the structure and properties of plasma sprayed alumina coating impregnated with aluminum phosphate
- 2016Rare-earth silicate crystallization in borosilicate glasses: Effect on structural and chemical durability propertiescitations
- 2016133 Cs and 23 Na MAS NMR Spectroscopy of Molybdate Crystallization in Model Nuclear Glassescitations
- 2015Impact of crystallization of apatite on the structure and chemical durability of borosilicate glass
- 2015Combining experimental and computational solid state NMR: A new tool for structure determination of borosilicate glass
- 2015Phase separation and crystallization effects on the structure and durability of molybdenum borosilicate glasscitations
- 2015Modélisation thermodynamique de l'interaction entre le verre et les phases molybdates.
- 2012Mechanism of RuO2 Crystallization in Borosilicate Glass: An Original in Situ ESEM Approachcitations
- 2012Effect of temperature and thermal history on borosilicate glass structurecitations
- 2011Quantification of boron by epma in nuclear glass
- 2011Behaviour of the Eu3+ D-5(0) -> F-7(0) transition in CaMoO4 powellite type ceramics under Ar and Pb ions implantationcitations
- 2011Insight into sodium silicate glass structural organization by multinuclear NMR combined with first-principles calculationscitations
- 2008Phase separation and crystallization in soda-lime borosilicate glass enriched in MoO3 studied by in situ Raman spectroscopy at high temperature
- 2008Phase separation and crystallization in soda-lime borosilicate glass enriched in MoO3 studied by in situ Raman spectroscopy at high temperature
- 2001Effect of cooling rate and heat treatment on ceramic microstructure and chemical durability. Materials Research Society Symposium
Places of action
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article
Discovery of a maximum damage structure for Xe-irradiated borosilicate glass ceramics containing powellite
Abstract
International audience ; In order to increase the waste loading efficiency in nuclear waste glasses, alternate glass ceramic (GC) materials are sought that trap problematic molybdenum in a water-durable CaMoO4 phase within a borosilicate glass matrix. In order to test the radiation resistance of these candidate wasteforms, accelerated external radiation can be employed to replicate long-term damage. In this study, several glasses and GCs were synthesized with up to 10 mol% MoO3 and subjected to 92 MeV Xe ions with fluences ranging between 5 × 1012 to 1.8 × 1014 ions/cm2. The main mechanisms of modification following irradiation involve: (i) thermal and defect-assisted diffusion, (ii) relaxation from the ion's added energy, (iii) localized damage recovery from overlapping ion tracks, and (iv) the accumulation of point defects or the formation of voids that created significant strain and led to longer-range modifications. Most significantly, a saturation in alteration could be detected for fluences greater than 4 × 1013 ions/cm2, which represents an average structure that is representative of the maximum damage state from these competing mechanisms. The results from this study can therefore be used for long-term structural projections in the development of more complex GCs for nuclear waste applications.