Summary
Biography
- Reader in Nuclear Engineering group, department of mechanical engineering: September 2022-Current.
- Senior lecturer in the Nuclear Engineering group, department of mechanical engineering: September 2019-August 2022.
- Lecturer in the Nuclear Engineering group, department of mechanical engineering: 2012-September 2019.
- Royal Academy of Engineering research fellow in the Department of Earth Science and Engineering: 2007-2012.
- Arthur William Groves research fellow in the Department of Earth Science and Engineering: 2004-2007.
- Judd Prize for PhD research: 2001.
- PhD, DIC, Computational Physics (Imperial College): 1998-2004.
- MSci, ARCS, Physics (Imperial College): 1993-1997.
Recent Measures of Esteem
- 2007-12 Royal Academy of Engineering/EPSRC Research Fellowship
Research Interests
Dr Eaton's research interests encompass: stochastic PDEs, uncertainty quantification, random processes, reactor noise, radiation transport in multiphase materials, high performance computing (HPC), GPUs and multicore distributed computing algorithms, radiative transfer, nuclear reactor physics, radiation shielding, nuclear criticality safety assessment, nuclear security and safeguards, space nuclear thermal propulsion and microscale nuclear reactors, fissile liquid and powder modelling, Generation IV NPP technology, SMR NPP technology, computational radiation transport (CRT), single and mulitphase computational fluid dynamics (CFD) and nuclear thermal-hydraulics, radiation detection technology, generative design optimisation. severe accident and nuclear safety, nuclear design optimisation, artificial neural networks (ANN), low source start-up and power ascension and radionuclide transport.
Additional Information
Matthew is the NEA databank representative for Imperial College and as such deals with the dissemination of nuclear data, computer programs and associated documentation.
Selected Publications
Journal Articles
Ferguson JA, Kópházi J, Eaton MD, 2022, NURBS enhanced virtual element methods for the spatial discretization of the multigroup neutron diffusion equation on curvilinear polygonal meshes, Journal of Computational and Theoretical Transport, Vol:51, ISSN:2332-4309, Pages:145-204
Jones GS, Winter GE, Cooling CM, et al., 2022, Mathematical and computational models for simulating transient nuclear criticality excursions within wetted fissile powder systems, Annals of Nuclear Energy, Vol:169, ISSN:0306-4549, Pages:1-31
Duan Y, North Ridao M, Eaton M, et al., 2022, Non-intrusive semi-analytical uncertainty quantification using Bayesian quadrature with application to CFD simulations, International Journal of Heat and Fluid Flow, Vol:93, ISSN:0142-727X, Pages:1-17
Lampunio L, Duan Y, Eaton MD, 2021, The effect of inlet flow conditions upon thermal mixing and conjugate heat transfer within the wall of a T-Junction, Nuclear Engineering and Design, Vol:385, ISSN:0029-5493, Pages:1-20
Welch J, Kophazi J, Owens A, et al., 2017, A geometry preserving, conservative, mesh-to-mesh isogeometric interpolation algorithm for spatial adaptivity of the multigroup, second-order even-parity form of the neutron transport equation, Journal of Computational Physics, Vol:347, ISSN:0021-9991, Pages:129-146