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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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Monnet, Isabelle
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (24/24 displayed)
- 2023Iron and steel corrosion mechanisms in a carbonate rich pore water: Multiscale characterization of the corrosion product layerscitations
- 2023Localised corrosion of iron and steel in the Callovo-Oxfordian porewater after 3 months at 120 °C: Characterizations at micro and nanoscale and formation mechanismscitations
- 2022Structural and mechanical modifications of GaN thin films by swift heavy ion irradiationcitations
- 2021Investigation of steel corrosion in MX80 bentonite at 120°Ccitations
- 2021Fullerene irradiation leading to track formation enclosing nitrogen bubbles in GaN materialcitations
- 2020Ionization-induced annealing in silicon upon dual-beam irradiationcitations
- 2019Swift heavy ion-irradiated multi-phase calcium borosilicates: implications to molybdenum incorporation, microstructure, and network topologycitations
- 2018Localized Plasmonic Resonances of Prolate Nanoparticles in a Symmetric Environment: Experimental Verification of the Accuracy of Numerical and Analytical Modelscitations
- 2018Irradiation and corrosion resistance of a nanostructured 316 austenitic stainless steel
- 2018Discovery of a maximum damage structure for Xe-irradiated borosilicate glass ceramics containing powellitecitations
- 2015In-situ characterization of ion-irradiation creep of micrometric SiC fibers
- 2015Irradiation and corrosion resistance of a nanostructured 316 austenitic stainless steel
- 2012Radiation Effects in Ceramics: Ceramics dislike strain, so they react to adapt
- 2012Formation of nanosized hills on Ti3SiC2 oxide layer irradiated with swift heavy ionscitations
- 2011In-situ X-Ray diffraction for ionic-covalent material study under swift heavy ion irradiation
- 2011Structural changes induced by heavy ion irradiation in titanium silicon carbidecitations
- 2010Effect of radiation-induced amorphization on smectite dissolution kinetics
- 2008Amorphization of sapphire induced by swift heavy ions: A two step process
- 2008Amorphization of ZnAl2O4 spinel under heavy ion irradiation
- 2008Effects of electronic and nuclear interactions in SiCcitations
- 2008Effect of the energy deposition modes on the structural stability of pure zirconiacitations
- 2005Plastic Deformation of Irradiated Zirconium Alloys: TEM Investigations and Micro-Mechanical Modelingcitations
- 2004Microstructural investigation of the stability under irradiation of oxide dispersion strengthened ferritic steels.
- 2004A statistical TEM investigation of dislocation channeling mechanism in neutron irradiated zirconium alloys.
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.