| 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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Tribet, Magaly
CEA Marcoule
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (11/11 displayed)
- 2024Impact of gamma dose rate on the alteration of nuclear glass in geological disposal conditions
- 2023Trivalent actinides and lanthanides incorporation in UMo glass-ceramicscitations
- 2023EPMA characterization of a radioactive nuclear glass sample
- 2022The impact of Al on the chemical durability of pristine and irradiated borosilicate glasses
- 2022Effects of complex irradiation scenarios on ISG nuclear glass long-term behavior
- 2021Effects of complex irradiation scenarios on ISG nuclear glass long-term behavior
- 2020New insights about the importance of the alteration layer/glass interfacecitations
- 2017Americium and trivalent Lanthanides incorporation in high-level waste glass-ceramicscitations
- 2017Radionuclides containment in nuclear glasses: an overviewcitations
- 2013Long-term aqueous alteration kinetics of an alpha-doped SON68 borosilicate glasscitations
- 2012Fabrication and characterization of americium, neptunium and curium bearing MOX fuels obtained by powder metallurgy processcitations
Places of action
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article
Radionuclides containment in nuclear glasses: an overview
Abstract
<jats:title>Abstract</jats:title><jats:p>Radioactive waste vitrification has been carried out industrially in several countries for nearly 40 years. Research into the formulation and long term behavior of high and intermediate level waste glasses, mainly borosilicate compositions, is still continuing in order to (i) safely condition new types of wastes and (ii) design and demonstrate the safety of the disposal of these long-lived waste forms in a deep geological repository. This article presents a summary of current knowledge on the formulation, irradiation resistance and the chemical durability of these conditioning materials, with a special focus on the fate of radionuclides during glass processing and aging. It is shown that, apart from the situation for certain elements with very low incorporation rate in glass matrices, vitrification in borosilicate glass can enable waste loadings of up to ~20 wt% while maintaining the glass homogeneity for geological time scales and guaranteeing a high stability level in spite of irradiation and water contact.</jats:p>