The PDRA project will seek to develop laser-based methods for characterisation of degraded spent nuclear fuel materials in situ. The techniques, including time-resolved laser fluorescence (TRLFS), Raman and laser-induced breakdown (LIBS) spectroscopy, provide direct speciation, structural and compositional information on uranium-containing compounds and solutions. Moreover, they offer the potential for ‘hands-off’ deployment, which is essential […]
Read moreUranium carbide (UC) is considered an exotic fuel material which has arisen from the UK nuclear test reactor programme. This material has served as both a fuel at sites like Dounreay, Scotland and as a fission target material in facilities such as CERN. The NDA has an inventory of irradiated uranium carbide as part of […]
Read moreThe overall aim of the PhD project and associated PDRA position is to construct the basis for a predictive tool for spent fuel behaviour; to model spent fuel in aqueous environments, across length-scales, using results from atomistic simulations, using physical and chemical kinetics, combining radiolysis models with molecular dynamics. We plan to close the loop […]
Read moreThe expected remaining lifetime of the UK’s Advanced Gas-cooled Reactors (AGRs) will result in the generation of ~6600t of Spent Nuclear Fuel. The Nuclear Decommissioning Authority’s preferred option for this spent fuel is pre-disposal interim storage – currently in ponds at Sellafield – prior to final disposal by consignment to a geologic disposal repository in […]
Read moreAim: To develop a better understanding of the properties and reactivity of bulk corrosion products arising from the degradation of legacy metallic and exotic SNF. Research will develop understanding of the fundamental properties and reactivity of bulk corrosion products arising from the degradation of legacy metallic and exotic nuclear fuel materials. Such research will […]
Read moreThere is a need to understand the stress corrosion cracking and mechanical properties of stainless steel 20-25-Nb AGR cladding material before and after irradiation to underpin predictions of structural integrity during transport and in storage and disposal environments. This PhD project aims to utilise real spent fuel clad materials recently provided to Bristol from the […]
Read moreThe PhD project will seek to investigate, experimentally and computationally, the corrosion mechanism(s), including intermediates, products and reaction rates, of spent nuclear fuel (SNF) in oxidative environments. The objective is therefore, to be able to predict quantitatively the degree of corrosion and product formation as a function of time and temperature by using a combination […]
Read moreA recently completed PhD project tested and proved the feasibility of drying AGR fuels that had been stored for long periods in a caustic environment. The project successfully developed a drying process and proved that end points can be identified. During the project, drying of perforated fuels was simulated in the main using pin […]
Read moreThe blind tube measurement of radiation to determine dose rate as a function of depth in contaminated land is performed currently with Geiger-Müller (GM) tubes on a push-rod cable. The former is installed in a water-proof housing and detects gamma radiation with which to infer the dose, whilst the latter is necessary to provide power […]
Read moreThe PhD project will seek to develop robust algorithms to predict gamma dose rates in contaminated pipelines based on limited direct information. The objective is to minimise and, where possible, avoid intrusive sampling and analysis while still acquiring sufficient information to justify management options (e.g. excavation, capping, leaving in situ) The focus will be on […]
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