Biography
Dr Ming (Eric) Jiang is currently a postdoctoral research associate in the Department of Engineering Science of University of Oxford, working with the Science and Technology Facilities Council (STFC). His work mainly includes investigating the thermomechanical properties of advanced materials at multiple length scales for challenging engineering applications.
Before joining the Department of Engineering Science in 2024, he completed his PhD study in the School of Physics of University of Bristol in 2024 with a PhD thesis titled 'Microstructural and Property Evolution of Nuclear Graphite under Extreme Conditions'. The main area of research in his PhD thesis is the irradiation-induced damage and microstructural evolution, as well as mechanical property evolution at elevated temperatures up to 1100°C in modern fine-grained nuclear graphite materials. These fine-grained graphite materials are candidate target materials for multi-megawatt (MW) class proton accelerators and key engineering materials for advanced graphite moderated nuclear fission reactors including HTGRs, VHTRs and MSRs.
He has been actively working with several leading industrial collaborators including U.S. Fermilab, UK NNL, EDF Energy, ISIS Neutron and Muon Source and UKAEA. He has also worked on TRISO fuel particles and medium- and high-entropy alloys using advanced imaging, micromechanical testing and in-situ beamline experimental techniques to understand their microstructures, residual stresses and multiscale deformation process under extreme conditions.
Dr Jiang obtained his Master of Engineering (MEng) from University of Bristol, working on FEA modelling of residual stress and plastic deformation of railway tracks under cyclic loading, supervised by Prof. Martyn Pavier. Dr Jiang also obtained his Master of Science (MSci) from University of Bristol working on microstructure and fracture of fine-grained nuclear graphite, supervised by Prof. Dong (Lilly) Liu.
Research Interests
- Advanced materials for nuclear and aerospace applications including nuclear graphite, TRISO fuel particles and ceramic matrix materials.
- Fracture mechanics and fracture micromechanisms in these novel materials and in situ mechanical testing at elevated temperatures.
- Applying novel experimental and numerical approaches at multiple length scales to study the thermomechanical property of these novel materials that have experienced extreme working environment.
- He has now developed interests in peridynamic modelling and Weibull statistical analysis of brittle and quasi-brittle materials.
Current Projects
- DUNE-LBNF Phase II
- EDF Energy graphite testing
- NNL TRISO particle
Research Groups
Related Academics
Publications
- Jiang M, Ell J, Barnard H, Wu H, Kuball M, Ritchie RO, Liu D. On the reduced damage tolerance of fine-grained nuclear graphite at elevated temperatures using in situ 4D tomographic imaging. Carbon. 2024;222:118924.
- Jiang M, Ammigan K, Lolov G, Pellemoine F, Liu D. Porosity evolution in proton irradiated microfine-grained POCO graphite. Journal of Nuclear Materials. 2023;587:154732.
- Jiang M, Ammigan K, Lolov G, Pellemoine F, Liu D. A novel method for quantifying irradiation damage in nuclear graphite using Raman spectroscopy. Carbon. 2023;213:118181.
- Liu D, Yu Q, Kabra S, Jiang M, Forna-Kreutzer P, Zhang R, et al. Exceptional fracture toughness of CrCoNi-based medium- and high-entropy alloys at 20 kelvin. Science. 2022;378(6623):978-83.
- Jordan MSL, Liu D, Jiang M, Tzelepi A. A Review of High-Temperature Characterization of Nuclear Graphites. In: Tzelepi A, Metcalfe M, editors. Graphite Testing for Nuclear Applications: The Validity and Extension of Test Methods for Material Exposed to Operating Reactor Environments. West Conshohocken, PA: ASTM International; 2022. p. 80-129.
- Jiang M, El-Turke A, Lolov G, Ammigan K, Hurh P, Liu D. Multiple length-scale microstructural characterisation of four grades of fine-grained graphite. Journal of Nuclear Materials. 2021;550:152876.
