Research themes
Professor Barry Marsden
- Graphite Moderated Reactors: Design, Operation, Safety, Decommissioning
- Microstructural studies on nuclear graphite using HRTEM, EELS, SEM, SIMS FIB-FEGSEM, XRD, X-ray-tomography, nano-indentation, RAMAN spectroscopy etc.
- Multi-scale modelling irradiated graphite behaviour using finite element techniques
- Graphite reactor component (moderator) structural assessment
- Fracture and failure in brittle materials
- Radiochemical characterisation with treatment and leaching behaviour of irradiated graphite waste
- Stored energy in irradiated graphite waste
- Strength and properties of carbon composites
- Statistical analysis of nuclear data, pattern recognition, model development
- Continuum damage mechanics model for nuclear graphite
- Crack Nucleation and Growth in Nuclear Graphite
- Microstructure/Property Relationships in Nuclear Graphite
- Advanced materials for fission and fusion applications
- Relationships between microstructure and properties in nuclear graphite
- Ultrascalable modelling of advanced materials with complex architectures
- Magnetic methods for residual stress measurement
- Valid property measurements at the microstructural scale