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Nuclear research in Materials
Luc Vandeperre
representing also
B. Britton, M. Wenman, D. Dye, M.P. Ryan, R. Grimes, & W.E. Lee
Staff with nuclear research in Materials
Engineering alloys Nanotechnology
Dr B. Britton, Prof D. Dye, Dr M. Wenman Prof Mary Ryan
Theory and simulation Ceramics & Glasses
Prof R. Grimes Prof. W. Lee Dr L. Vandeperre Dr N.Ni
Ben Britton
• Heterogeneous Deformation in Zirconium Alloys
• The Crystallographic Texture Evolution in Two-phase (hcp/bcc) Alloys
• Discrete Dislocation Dynamics coupled with Discrete Solute Diffusion
to Model the Effect of Hydrogen in Steel
• Highlight : Slip strengths for the different slip systems in Zr
J. Gong, T.B. Britton, M.A. Cuddihi, F.P.E. Dunne, A.J. Wilkinson,
<a> Prismatic, <a> basal and <c+a> slip strengths of commercially
pure Zr by micro-cantilever tests, Acta Materialia, 96, 2015, 249-
257
David Dye
Hydrides in Zircaloy 4
Highlight : In Situ Micropillar Deformation of Hydrides in Zircaloy-4
Weekes HE, Vorontsov VA, Dolbnya IP, Plummer
JD, Giuliani F, Britton TB, Dye D et al., 2015, In
situ micropillar deformation of hydrides in Zircaloy-
4, ACTA MATERIALIA, Vol: 92, Pages: 81-96
Mark Wenman
• Cl-Induced Transgranular SCC of Austenitic Stainless Steel 304L
• FEM of Pellet Clad Interaction in Advanced Gas-Cooled Reactors
• Inverse Numerical Method for Calculating the Temperature Dependent
Thermal Conductivity of Nuclear Materials
Highlight : Modelling fracture of nuclear fuel pellets
R. Mella, M.R. Wenman, Modelling explicit fracture
of nuclear fuel pellets using peridynamics, Journal
of Nuclear Materials, 467, 2015, 58-67
Mary Ryan
• Nanoscale Investigation and Control of Radionuclides in Waste
Management
• Adsorption of radionucleides on cement phases
Highlight : Advanced spectroscopy to study surface interactions
A. van Veelen , O. Preedy , J. Qi, GTW Law, K Morris, JFW Mosselmans , MP Ryan, NDM Evans, RA
Wogelius, Uranium and technetium interactions with wustite [Fe1-xO] and portlandite [Ca(OH)(2)] surfaces
under geological disposal facility conditions, MINERALOGICAL MAGAZINE, 78, 2014, 1097-1113
EXAFS XANES
Robin Grimes
• Atomistic Simulation of Dislocation Creep in UO2 Nuclear Fuel
• Fundamental Properties of Thoria Based Mixed Oxides
• Atomic Scale Modelling of Hydrogen Pickup in Zr Based Fuel Cladding
• Atomistic Modelling of Alloys and Intermetallics for Nuclear
Applications
• Method for Calculating the Thermal Conductivity of Nuclear Materials
• Simulation of Materials for Nuclear Fusion Reactors
• Atomic-scale Simulation of Mixed Oxide and Conventional Nuclear
Fuel
• Atomistic Simulation of Fission Products in Zirconia using DFT
• Atomistic Simulation of UK Spent Nuclear Fuel
Bill Lee
• MAX Phases for Accident-Tolerant Fuels
• ZrC and MAX Phases for Future Fission Environments
• Diffusion Properties and Processing of Non-Stoichiometric ZrC
• Processing and Characterisation of ZrCxNy as a Function of
Stoichiometry via Carbothermic Reduction
• Low Melting Glass Wasteforms for Fukushima Absorbing Membranes
• Modelling the Thermal Output of High Dose Spent Absorbents used in
the Clean-up of Fukushima
• Surface Analysis of Simulant UK High Level Waste Glass
• Immobilisation Options for Exotic Carbide Fuels
• Glass Composite Materials for Radioactive Waste Immobilisation
• Processing and Microstructural Characterisation of UO2-based
Simulated Spent Nuclear Fuel Ceramics for the UK`s Advanced Gas-
cooled Reactors
• Virtual Reality in Nuclear Decommissioning
Bill Lee
Highlight : Modelling the Thermal Output of High Dose Spent
Absorbents used in the Clean-up of Fukushima
Large quantities of Cs and Sr on adsorbents from cleaning water
Cs and Sr high doses and short half-lives but are Short Lived ILW
Current wasteform under development
is low melting point glass
Research question : can heat from
radionucleide decay be used to self-densify
the glass frit into a wasteform ?
Sintering parameter optimisation performed with cold-pressed 10 wt.% waste
loading
Na Ni
• Study of corrosion mechanisms of MAX phase materials
Highlight : Study of Oxidation of Zirconium Alloys by Electron Microscopy
N. Ni, D. Hudson, et al., How
the crystallography and
nanoscale chemistry of the
metal/oxide interface
develops during the aqueous
oxidation of zirconium
cladding alloys, Acta
Materialia, 60, 2012, 7132-
7149
Luc Vandeperre
• Modelling the Thermal Output of High Dose Spent Absorbents used in
the Clean-up of Fukushima
• Nanoscale Investigation and Control of Radionuclides in Waste
Management
• Adsorption of radionucleides on cement phases
Highlight : CO32- & Cl- capture with layered double hydroxides
Phillips JD, Vandeperre LJ, 2011, Anion capture with calcium,
aluminium and iron containing layered double hydroxides,
JOURNAL OF NUCLEAR MATERIALS, Vol: 416, Pages: 225-229
Thank you – questions ?
Engineering alloys
Ben Britton [email protected]
Mark Wenman [email protected]
David Dye [email protected]
Nanotechnology
Mary Ryan [email protected]
Theory and Simulations of Materials
Robin Grimes [email protected]
Ceramics and Glasses
Bill Lee [email protected]
Na Ni [email protected]
Luc Vandeperre [email protected]