| People | Locations | Statistics |
|---|---|---|
| Naji, M. |
| |
| Motta, Antonella |
| |
| Aletan, Dirar |
| |
| Mohamed, Tarek |
| |
| Ertürk, Emre |
| |
| Taccardi, Nicola |
| |
| Kononenko, Denys |
| |
| Petrov, R. H. | Madrid |
|
| Alshaaer, Mazen | Brussels |
|
| Bih, L. |
| |
| Casati, R. |
| |
| Muller, Hermance |
| |
| Kočí, Jan | Prague |
|
| Šuljagić, Marija |
| |
| Kalteremidou, Kalliopi-Artemi | Brussels |
|
| Azam, Siraj |
| |
| Ospanova, Alyiya |
| |
| Blanpain, Bart |
| |
| Ali, M. A. |
| |
| Popa, V. |
| |
| Rančić, M. |
| |
| Ollier, Nadège |
| |
| Azevedo, Nuno Monteiro |
| |
| Landes, Michael |
| |
| Rignanese, Gian-Marco |
|
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
| Organizations | Location | People |
|---|
article
Immobilisation of Prototype Fast Reactor raffinate in a barium borosilicate glass matrix
Abstract
The vitrification of Dounreay Prototype Fast Reactor (PFR) Raffinate in a barium borosilicate glass matrix was investigated, with the aim of understanding process feasibility and the potential benefits over the current baseline of cement encapsulation. Laboratory scale glass melts demonstrated the production of homogeneous glasses incorporating at least 20 wt% simulant PFR waste (on an oxides basis), with no detectable crystalline accessory phases. The hardness and indentation fracture toughness of the simulant PFR waste glasses were determined to be comparable to those of current UK high level waste glass formulations. The normalised dissolution rate of boron from the simulant PFR glasses was determined to be 3 × 10−2 g m-2 d-1, in 18.2 MΩ water at 90 °C and surface area/volume ratio of 1500 m−1, only a factor of two greater than the French SON-68 simulant high level waste glass, under comparable conditions. Consequently, the simulant PFR waste glasses show considerable promise for meeting envisaged waste acceptance criteria for geological disposal. Overall, the superior stability of vitrified PFR wasteforms could enhance the safety case for long term near surface storage of radioactive wastes, mandated by current Scottish Government policy.