David Hambley
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View article: Position-sensitive neutron detection via a capture γ-ray proxy for water assay in spent nuclear fuel
Position-sensitive neutron detection via a capture γ-ray proxy for water assay in spent nuclear fuel Open
The potential to exploit 2.223 MeV capture γ rays for the position sensitive detection of neutrons as a proxy for water in spent nuclear fuel is described. Previously, we demonstrated from a modelling perspective that the extent to which w…
View article: Microstructural analysis of ex-service neutron irradiated stainless steel nuclear fuel cladding by high-speed AFM
Microstructural analysis of ex-service neutron irradiated stainless steel nuclear fuel cladding by high-speed AFM Open
Fuel cladding in advanced gas-cooled nuclear reactors is made of an austenitic stainless steel referred to as 20Cr/25NiNb. This material can undergo microstructural changes in these extreme environments through a combination of thermal eff…
View article: Microstructural Analysis of Ex-Service Neutron Irradiated Stainless Steel Nuclear Fuel Cladding by High-Speed Afm
Microstructural Analysis of Ex-Service Neutron Irradiated Stainless Steel Nuclear Fuel Cladding by High-Speed Afm Open
View article: AGR fuel corrosion: SIMFUEL-based method development in preparation for electrochemical studies of real spent AGR nuclear fuel electrode
AGR fuel corrosion: SIMFUEL-based method development in preparation for electrochemical studies of real spent AGR nuclear fuel electrode Open
Electrochemical corrosion of lower-activity spent fuel simulants, SIMFUELs, has been investigated in support of on-going analogous studies of a real AGR spent nuclear fuel electrode. Two electrode coupling methods have been investigated, t…
View article: Simulated advanced gas-cooled reactor spent nuclear fuels: Determination of the O/U ratio - an XRD, XPS and Raman study
Simulated advanced gas-cooled reactor spent nuclear fuels: Determination of the O/U ratio - an XRD, XPS and Raman study Open
This paper reports a detailed chemical and materials characterization study of novel Simulated Spent Nuclear Fuels (SIMFuel) which replicate the chemical and microstructural state of Spent Nuclear Fuel (SNF) discharged from a UK Advanced G…
View article: A geometrical model to describe the alpha dose rates from particulates of UO2 in water
A geometrical model to describe the alpha dose rates from particulates of UO2 in water Open
View article: A mathematical model to describe the alpha dose rate from a UO2 surface
A mathematical model to describe the alpha dose rate from a UO2 surface Open
View article: Raman studies of advanced gas-cooled reactor simulated spent nuclear fuels
Raman studies of advanced gas-cooled reactor simulated spent nuclear fuels Open
Analysis of advanced gas-cooled reactor (AGR) simulated used nuclear fuels (SIMFuels) has been carried out using micro-Raman spectroscopy in order to understand the effect lanthanide species (e.g.Nd, Y, Ce), representative of fission produ…
View article: The behavior of advanced gas reactor simulated spent nuclear fuels in wet interim storage conditions
The behavior of advanced gas reactor simulated spent nuclear fuels in wet interim storage conditions Open
The safe interim storage of spent nuclear fuel is important to prevent the degradation of the containers and fuel rods -both fuel pellets and cladding -thus avoiding the release of radiation and allowing the fuel to be safely handled on tr…
View article: Permeability of observed three dimensional fracture networks in spent fuel pins
Permeability of observed three dimensional fracture networks in spent fuel pins Open
The three-dimensional fracture network within a spent fuel pin is characterised using sequential grinding, and its permeability is numerically estimated. Advanced Gas-cooled Reactors (AGRs) produce spent fuel pins consisting of an outer st…
View article: Lessons learned from a review of international approaches to spent fuel management
Lessons learned from a review of international approaches to spent fuel management Open
\nWorldwide, a variety of approaches to the management of spent fuel have been adopted. A review of approaches adopted internationally was undertaken to inform decision making on spent fuel management in UK. The review surveyed spent fuel …
View article: Storage of thermal reactor fuels – Implications for the back end of the fuel cycle in the UK
Storage of thermal reactor fuels – Implications for the back end of the fuel cycle in the UK Open
\nFuel from UK's Advanced Gas-Cooled Reactors (AGRs) is being reprocessed, however reprocessing will cease in 2018 and the strategy for fuel that has not been reprocessed is for it to be placed into wet storage until it can be consigned to…
View article: Corrosion of AGR Fuel Pin Steel Under Conditions Relevant to Permanent Disposal
Corrosion of AGR Fuel Pin Steel Under Conditions Relevant to Permanent Disposal Open
Fuel pins from the UK's Advanced Gas-cooled Reactors (AGR) consist of ceramic UO2 fuel encased in a 20/25/Nb stainless steel cladding. Spent AGR fuel is currently reprocessed, but the option of direct disposal of spent fuel in a sealed, un…