Energy (Nuclear) Materials
Welcome to Energy Materials
Introduction
The Energy Materials website is intended to be a gateway to the broad range of energy-related materials research at Oxford University, particularly in the Materials Department. At the present time, it focussed on materials for nuclear fission and nuclear fusion power. The nuclear fission research is aimed at current and next generation plant (including Generation IV). Many fundamental issues are common to both fission and fusion.
.png "Atomic scale study of oxide dispersion strengthened steels")
.png "Atomic scale study of oxide dispersion strengthened steels")
.png "Deformation and Fracture of Concrete Microstructures")
.png "Deformation and Fracture of Concrete Microstructures")
.png "Hydride Cracking In Zirconium")
.png "Hydride Cracking In Zirconium")
.png "The Effects of Neutron Radiation On Oxide Dispersion Strengthened Steels")
.png "The Effects of Neutron Radiation On Oxide Dispersion Strengthened Steels")
.png "Three-dimensional damage nucleation in energy.materials")
.png "Three-dimensional damage nucleation in energy.materials")
.jpg "Micromechanical Modelling")
(1).png "Mimicking Neutron Damage in Tungsten using self ion implantation")
(2).png "Mimicking Neutron Damage in Tungsten using self ion implantation")
(3).png "Mimicking Neutron Damage in Tungsten using self ion implantation")
.png "Variable Temperature Nanoindentation")
.png "Powder processing of ODS alloys for nuclear applications")
.png "Powder processing of ODS alloys for nuclear applications")
.png "Powder processing of ODS alloys for nuclear applications")
Site Content
The site contains brief details of current and past projects. Links are provided to external websites where you can find more information on the techniques and facilities available. Links are also provides to our many collaborators and partners.
If you think your work should be included or linked to, please do contact me.
Thank you
James Marrow (james.marrow@materials.ox.ac.uk)
Next page: Members
Atomic scale study of oxide dispersion strengthened steels
Dislocation network in ODS-Eurofer 97, before and after ion implantationAtomic scale study of oxide dispersion strengthened steels
Ti-Y-O clusters in EPFL-14Cr-2W-0.3Ti & Y2O3 ODS steelDeformation and Fracture of Concrete Microstructures
Evolution of the compressive damage in a concrete specimen, studied with tomography and digital volume correlationDeformation and Fracture of Concrete Microstructures
Nominal strain field within one 2D slice of a 3D dataset, in which an initiated crack is visible, compared with the microstructureHydride Cracking In Zirconium
Triangular Cantilever for testing Elastic PropertiesHydride Cracking In Zirconium
Local misorientation around indents made in pure Zr measured using EBSDMicromechanical testing of SCC Behaviour at Individual Grain Boundaries
Micromechanical test specimen for stress corrosion cracking of a grain boundaryPowder processing of ODS alloys for nuclear applications
ODS powder milled for 8hours in the planetary ball millRadiation Damage in Iron-based alloys
Ion Radiation damage in Fe 11%CrSmall scale mechanics applied to nuclear materials
FIB-milled cantilever in FeThe Effects of Neutron Radiation On Oxide Dispersion Strengthened Steels
A FIB lift out with protective platinum layer from helium implanted Eurofer 97 oxide dispersion strengthened steel at 1um under focusThe Effects of Neutron Radiation On Oxide Dispersion Strengthened Steels
Helium bubbles in Eurofer 97 oxide dispersion strengthened steel at 1um under and over focusThree-dimensional damage nucleation in energy.materials
Visualization, via strain mapping, of a crack inside a short-rod, chevron notched poly-granular graphite sampleThree-dimensional damage nucleation in energy.materials
A horizontal slice through the strain field measured within a short-rod, chevron notched poly-granular graphite sampleMicromechanical Modelling
Dislocation dynamic simulation of micro-cantilever beamMimicking Neutron Damage in Tungsten using self ion implantation
Atomic Force Microscope Scans of nanoindents in W5wt%Ta at differing ion damage levels showing change in pile up structureMimicking Neutron Damage in Tungsten using self ion implantation
Ion Implantation of Tungsten 800oC at CEA Saclay, FranceMimicking Neutron Damage in Tungsten using self ion implantation
Ion Implantation of Tungsten 800oC at CEA Saclay, FranceVariable Temperature Nanoindentation
Array of identical micro-cantilevers for high temperature fracture testing at 750oCPowder processing of ODS alloys for nuclear applications
Transmission electron microscopy image of ODS powder particle after mechanical alloying for 60 hrs and 1 hr annealing at 700°C.Powder processing of ODS alloys for nuclear applications
Atom probe topography maps from an ODS powder particle after mechanical alloying showing a homogeneous distribution of yttrium and chromium throughout the sample volume.Powder processing of ODS alloys for nuclear applications
EBSD image of bulk ODS with composition of Fe-14Cr-3W-0.2Ti-0.25Y2O3 (wt%) produced by a novel sintering technique, spark plasma sintering. It shows that our ODS exhibit high density and bimodal grain size.