Nuclear research in Materials

Luc Vandeperre

l.vandeperre@imperial.ac.uk

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 b.britton@imperial.ac.uk

Mark Wenman m.wenman@imperial.ac.uk

David Dye david.dye@imperial.ac.uk

Nanotechnology

Mary Ryan m.p.ryan@imperial.ac.uk

Theory and Simulations of Materials

Robin Grimes r.grimes@imperial.ac.uk

Ceramics and Glasses

Bill Lee w.e.lee@imperial.ac.uk

Na Ni n.ni@imperial.ac.uk

Luc Vandeperre l.vandeperre@imperial.ac.uk