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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
Investigation of the electronic and geometric structures of the (110) surfaces of arsenopyrite (FeAsS) and enargite (Cu3AsS4)
Abstract
The (110) surfaces of arsenopyrite (FeAsS) and enargite (Cu 3AsS4) have been modelled using a Density Functional Theory (DFT) plane-wave pseudopotential method (CASTEP) in order to better understand aspects of the geometric and electronic structures of these minerals, which have important implications for the release of arsenic in acid mine drainage environments. In this study, bulk calculations of these minerals have been conducted to give consistent geometries for surface models and to establish reference states for changes at the surfaces in these models. Surface structure experimental data for enargite were collected using low-energy electron diffraction which confirmed an unreconstructed 1 × 1 (110) lattice, with a and b values of 6.38±0.3 Å and 9.92±0.5 Å, respectively. Surface calculations demonstrate geometric and electronic relaxation of both arsenopyrite and enargite (110) surfaces. Changes in atomic positions, interatomic distances, Mulliken charges and electronic configurations are reported. Enargite has a surface energy of ∼0.02 eV/Å2 compared with arsenopyrite which has a surface energy of ∼0.11 eV/Å2, indicating that the enargite (110) surface is more energetically stable than that of arsenopyrite. The most stable surfaces are those which relax to restore the surface coordination and partial charge balance. For both minerals this is achieved by the formation of covalent bonds. Arsenic has the most positive Mulliken charge of all the surface atoms and is, therefore, predicted to be the most reactive atom at the arsenopyrite and enargite (110) surfaces. This implies that, according to these calculations, arsenic is most likely to react with oxidative species such as O2 and H2O in environments such as those associated with acid mine drainage, potentially releasing oxides and acids of arsenic into the environment. © 2011 Mineralogical Society.