Department: Materials
Organisation: University of Oxford
Miniature Ultrasonic Fatigue Analysis of Local Modified Regions near Welds and Surfaces in Ti alloys
Advanced Nuclear Materials
Ceramic Coatings for Clad (The C^3 Project): Advanced Accident-Tolerant Ceramic Coatings for Zr-alloy Cladding
Characterisation of Nanomaterials for Energy
Heterogeneous Mechanics in Hexagonal Alloys across Length and Time Scales
Ion irradiations of fusion reactor materials
MIDAS - Mechanistic understanding of Irradiation Damage in fuel Assemblies
Materials for fusion & fission power
Micromechanical Modelling and Experimentation
Predictive Modelling of Mechanical Properties of Materials for Fusion Power Plants
RADIATION RESISTANT HIGH ENTROPY ALLOYS FOR FAST REACTOR CLADDING APPLICATIONS
Simultaneous Corrosion/Irradiation Testing in Lead and Lead-Bismuth Eutectic: The Radiation Decelerated Corrosion Hypothesis (RC-3)
Understanding the mechanisms controlling low potential stress corrosion cracking in nuclear reactors
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