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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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Corkhill, Claire L.
University of Bristol
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (32/32 displayed)
- 2024A disposal-MOX concept for plutonium dispositioncitations
- 2023Underpinning the use of indium as a neutron absorbing additive in zirconolite by X-ray absorption spectroscopycitations
- 2023Investigation of the effect of milling duration on a Ce-Gd doped zirconolite phase assemblage synthesised by hot isostatic pressingcitations
- 2023A Review of Zirconolite Solid Solution Regimes for Plutonium and Candidate Neutron Absorbing Additivescitations
- 2023Micro- and Nanoscale Surface Analysis of Late Iron Age Glass from Broborg, a Vitrified Swedish Hillfortcitations
- 2022Characterisation of a Complex CaZr0.9Ce0.1Ti2O7 Glass–Ceramic Produced by Hot Isostatic Pressingcitations
- 2022Characterisation of a Complex CaZr 0.9 Ce 0.1 Ti 2 O 7 Glass–Ceramic Produced by Hot Isostatic Pressingcitations
- 2022Investigating the mechanical behaviour of Fukushima MCCI using synchrotron Xray tomography and digital volume correlationcitations
- 2021Early age hydration and application of blended magnesium potassium phosphate cements for reduced corrosion of reactive metalscitations
- 2021Synthesis of Ca1-xCexZrTi2-2xAl2xO7 zirconolite ceramics for plutonium dispositioncitations
- 2021Synthesis of Ca 1-x Ce x ZrTi 2-2x Al 2x O 7 zirconolite ceramics for plutonium dispositioncitations
- 2021Investigating the microstructure and mechanical behaviour of simulant "lava-like" fuel containing materials from the Chernobyl reactor unit 4 meltdowncitations
- 2021Characterisation and durability of a vitrified wasteform for simulated Chrompik III waste
- 2021Thermal treatment of Cs-exchanged chabazite by hot isostatic pressing to support decommissioning of Fukushima Daiichi nuclear power plantcitations
- 2021Synthesis and characterisation of HIP Ca 0.80 Ce 0.20 ZrTi 1.60 Cr 0.40 O 7 zirconolite and observations of the ceramic–canister interfacecitations
- 2021Synthesis and characterisation of HIP Ca0.80Ce0.20ZrTi1.60Cr0.40O7 zirconolite and observations of the ceramic–canister interfacecitations
- 2020Characterization of Cebama low-pH reference concrete and assessment of its alteration with representative waters in radioactive waste repositoriescitations
- 2020Synthesis and in situ ion irradiation of A-site deficient zirconate perovskite ceramicscitations
- 2019Investigation of the role of Mg and Ca in the structure and durability of aluminoborosilicate glasscitations
- 2019The Formation of Pitted Features on the International Simple Glass during Dynamic Experiments at Alkaline pHcitations
- 2019Physical and optical properties of the International Simple Glasscitations
- 2018Dissolution of glass in cementitious solutionscitations
- 2018Development, characterization and dissolution behavior of calcium-Aluminoborate glass wasteforms to immobilize rare-earth oxidescitations
- 2018Immobilisation of Prototype Fast Reactor raffinate in a barium borosilicate glass matrixcitations
- 2018Response to the discussion by Hongyan Ma and Ying Li of the paper “Characterization of magnesium potassium phosphate cement blended with fly ash and ground granulated blast furnace slag”citations
- 2018Dissolution of glass in cementitious solutions:An analogue study for vitrified waste disposalcitations
- 2017Synthesis of simulant 'lava-like' fuel containing materials (LFCM) from the Chernobyl reactor Unit 4 meltdowncitations
- 2016Alteration layer formation of Ca- and Zn-oxide bearing alkali borosilicate glasses for immobilisation of UK high level wastecitations
- 2013Technetium-99m transport and immobilisation in porous mediacitations
- 2013Advanced ceramic wasteforms for the immobilisation of radwastes
- 2011Investigation of the electronic and geometric structures of the (110) surfaces of arsenopyrite (FeAsS) and enargite (Cu3AsS4)citations
- 2008The oxidative dissolution of arsenopyrite (FeAsS) and enargite (Cu3AsS4) by Leptospirillum ferrooxidanscitations
Places of action
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article
Characterization of Cebama low-pH reference concrete and assessment of its alteration with representative waters in radioactive waste repositories
Abstract
<p>Concretes, mortars and grouts are used for structural and isolation purposes in radioactive and nuclear waste repositories. For example, concrete is used for deposition tunnel end plugs, engineered barriers, mortars for rock bolting and injection grouts for fissure sealing. Despite of the materials anticipated functionality, it is extremely important to understand the long-term material behaviour in repository environments. A reference concrete and mortar for the Cebama project based on a cement, silica and blast furnace slag ternary blend were designed and characterized in different laboratories with multiple experimental methods (XRD, XAS at the Fe and Cl K-edges, SEM-EDX, <sup>29</sup>Si and <sup>27</sup>Al MAS-NMR, TG-DSC, MIP and Kerosene porosimetry) and techniques (punch strength tests). The reference concrete enabled comparison of results from different institutes and experimental techniques, unifying the individual results to more comprehensive body. The Cebama reference concrete and mortar were designed to have high durability and compatible formulation with respect to an engineered barrier system in clay or crystalline host-rocks, having pore solution pH significantly lower than traditional concretes. This work presents main results regarding their characterization and alteration in contact with representative waters present in radioactive waste repositories. Pore solution pH of the matured reference concrete was 11.4–11.6. The main hydrated phases were C–S–H and C-A-S-H gels with a Ca:Si ratio between 0.5 and 0.7 and an Al:Si ratio of 0.05. Minor phases were ettringite and hydrotalcite. Iron(III) could be in the C–S–H phases and no Cl-bearing solid phases were identified. Connected porosity and pore size distribution was characterized by MIP observing that, as expected, the size of the pores in the hydrated cement phases varies from the micro-to the nanoscale. Connected porosity of both materials were low. Compressive strength of the concrete was 115 MPa, corresponding to traditional high-performance concrete. Degradation of these materials in contact with different waters mainly produce their decalcification and enrichment in Mg for waters containing high amount of this element, like the clay waters.</p>