| EP/T016728/1 | Cobalt-free Hard-facing for Reactor Systems | (C) |
| EP/S021663/1 | A LEAP 5000 XS for the UK National Atom Probe Facility | (C) |
| EP/S019367/1 | The Royce: Capitalising on the investment | (C) |
| EP/R000956/1 | Silicide-Strengthened Steel - A New Method of Wear Protection within Nuclear Environments | (P) |
| EP/P005284/1 | An integrated (ICME) approach to multiscale modelling of the fabrication and joining of powder processed parts | (C) |
| EP/P006566/1 | MAPP: EPSRC Future Manufacturing Hub in Manufacture using Advanced Powder Processes | (C) |
| EP/M018369/1 | From Processing to Simulated In-Reactor Performance of Zr Cladding. | (P) |
| EP/K039237/2 | Ceramic Coatings for Clad (The C^3 Project): Advanced Accident-Tolerant Ceramic Coatings for Zr-alloy Cladding | (C) |
| EP/M018482/1 | Carbides for Future Fission Environments (CAFFE) | (C) |
| EP/M022803/1 | LEAP 5000XR for the UK National Atom Probe Facility | (C) |
| EP/M000737/1 | Dislocation-Microstructure Interaction at a Crack Tip - In Search of a Driving Force for Short Crack Growth | (P) |
| EP/M005607/1 | Strategic Partnership in Structural Metallic Systems for Gas Turbines | (C) |
| EP/L025981/1 | High Fidelity Ion Beam Simulation of High Dose Neutron Irradiation | (P) |
| EP/L018616/1 | PACIFIC - Providing a Nuclear Fuel Cycle in the UK for Implementing Carbon Reductions | (C) |
| EP/K034650/1 | Engineered Zircaloy Cladding Modifications for Improved Accident Tolerance of LWR Fuel | (P) |
| EP/K039237/1 | Ceramic Coatings for Clad (The C^3 Project): Advanced Accident-Tolerant Ceramic Coatings for Zr-alloy Cladding | (C) |
| EP/K034332/1 | Heterogeneous Mechanics in Hexagonal Alloys across Length and Time Scales | (C) |
| EP/J021172/1 | New Nuclear Manufacturing (NNUMAN) | (P) |
| EP/I012346/1 | Irradiation Effects on Flow Localisation in Zirconium Alloys | (P) |
| EP/I005420/1 | Enhancing nuclear fuel efficiency through improved understanding of irradiation damage in zirconium cladding | (P) |
| EP/I003290/1 | Performance and Reliability of Metallic Materials for Nuclear Fission Power Generation | (P) |
| EP/H020047/1 | LIGHT ALLOYS TOWARDS ENVIRONMETALLY SUSTAINABLE TRANSPORT: 2nd GENERATION SOLUTIONS FOR ADVANCED METALLIC SYSTEMS (LATEST2) | (C) |
| EP/F020910/1 | Strain mapping of individual grains using diffraction contrast tomography | (P) |
| EP/E058817/1 | Fatigue Crack Growth in Complex Residual Stress Fields due to Surface Treatment and Foreign Object Damage under Simulated Flight Cycles | (C) |
| EP/E048455/1 | Effective Structural Unit Size in Polycrystals: Formation, Quantification and Micromechanical Behaviour | (P) |
| EP/E020933/1 | A fundamental study of deformation mechanisms in advanced polycrystalline nickel-base superalloys | (P) |
| EP/E036171/1 | Zirconium alloys for high burn-up fuel in current and advanced light water-cooled reactors | (P) |
| EP/C008847/1 | FaME38 - Exploitation and Development of the Joint Support Facility for Materials Engineering at the ILL-ESRF as a UK Collaborative Research Group | (C) |
| GR/T19711/01 | The relation between internal stress & failure in TiAl-based alloys and in a burn-resistant Ti alloy | (C) |
| EP/C002946/1 | Crack Nucleation and Short Crack Behaviour by Non-destructive In-situ Observation | (C) |
| EP/C00194X/1 | A SCIENTIFIC BASE FOR LASER NET SHAPING OF SUPERALLOYS WITH CUSTOM DISTRIBUTED PROPERTIES | (C) |
| GR/R99089/01 | Micromechanics of TI/SIC Fibre Composites | (C) |