| Baseline high heat flux and plasma facing materials for fusion Y Ueda, K Schmid, M Balden, JW Coenen, T Loewenhoff, A Ito, ... Nuclear Fusion 57 (9), 092006, 2017 | 170 | 2017 |
| Effects of irradiation temperature and dose rate on the mechanical properties of self-ion implanted Fe and Fe–Cr alloys CD Hardie, CA Williams, S Xu, SG Roberts Journal of Nuclear Materials 439 (1-3), 33-40, 2013 | 131 | 2013 |
| Progress in the realization of the PRIMA neutral beam test facility V Toigo, D Boilson, T Bonicelli, R Piovan, M Hanada, A Chakraborty, ... Nuclear Fusion 55 (8), 083025, 2015 | 127 | 2015 |
| Understanding the effects of ion irradiation using nanoindentation techniques CD Hardie, SG Roberts, AJ Bushby Journal of Nuclear Materials 462, 391-401, 2015 | 110 | 2015 |
| Small-scale characterisation of irradiated nuclear materials: Part II nanoindentation and micro-cantilever testing of ion irradiated nuclear materials DEJ Armstrong, CD Hardie, J Gibson, AJ Bushby, PD Edmondson, ... Journal of Nuclear Materials 462, 374-381, 2015 | 102 | 2015 |
| Nanoindentation of model Fe–Cr alloys with self-ion irradiation CD Hardie, SG Roberts Journal of Nuclear materials 433 (1-3), 174-179, 2013 | 76 | 2013 |
| First dust study in JET with the ITER-like wall: sampling, analysis and classification A Baron-Wiechec, E Fortuna-Zaleśna, J Grzonka, M Rubel, A Widdowson, ... Nuclear Fusion 55 (11), 113033, 2015 | 72 | 2015 |
| Effects of neutron irradiation on the brittle to ductile transition in single crystal tungsten RG Abernethy, JSKL Gibson, A Giannattasio, JD Murphy, O Wouters, ... Journal of Nuclear Materials 527, 151799, 2019 | 39 | 2019 |
| Nanoindentation investigation of ion-irradiated Fe–Cr alloys using spherical indenters AJ Bushby, SG Roberts, CD Hardie Journal of Materials Research 27 (1), 85-90, 2012 | 35 | 2012 |
| Scratching the surface: Elastic rotations beneath nanoscratch and nanoindentation tests A Kareer, E Tarleton, C Hardie, SV Hainsworth, AJ Wilkinson Acta Materialia 200, 116-126, 2020 | 31 | 2020 |
| Spherical indentation of copper: Crystal plasticity vs experiment AJ Cackett, CD Hardie, JJH Lim, E Tarleton Materialia 7, 100368, 2019 | 22 | 2019 |
| Tungsten-based bcc-superalloys AJ Knowles, D Dye, RJ Dodds, A Watson, CD Hardie, SA Humphry-Baker Applied Materials Today 23, 101014, 2021 | 21 | 2021 |
| Design and R&D for manufacturing the beamline components of MITICA and ITER HNBs M Dalla Palma, E Sartori, P Blatchford, B Chuilon, J Graceffa, S Hanke, ... Fusion Engineering and Design 96, 557-562, 2015 | 20 | 2015 |
| Residual stress generation in brazed tungsten dissimilar joints D Easton, J Wood, S Rahimi, A Galloway, Y Zhang, C Hardie IEEE Transactions on Plasma Science 44 (9), 1625-1630, 2016 | 19 | 2016 |
| Using spherical indentation to measure the strength of copper-chromium-zirconium AJ Cackett, JJH Lim, P Klupś, AJ Bushby, CD Hardie Journal of Nuclear Materials 511, 610-616, 2018 | 17 | 2018 |
| Mechanical properties and plasticity size effect of Fe-6% Cr irradiated by Fe ions and by neutrons CD Hardie, GR Odette, Y Wu, S Akhmadaliev, SG Roberts Journal of Nuclear Materials 482, 236-247, 2016 | 17 | 2016 |
| Brazing development and interfacial metallurgy study of tungsten and copper joints with eutectic gold copper brazing alloy D Easton, Y Zhang, J Wood, A Galloway, MO Robbie, C Hardie Fusion Engineering and Design 98, 1956-1959, 2015 | 17 | 2015 |
| Simulation of crystal plasticity in irradiated metals: A case study on Zircaloy-4 C Hardie, R Thomas, Y Liu, P Frankel, F Dunne Acta Materialia 241, 118361, 2022 | 16 | 2022 |
| Effects of radiation damage and precipitate distribution on micro-pillar compression testing of irradiated CuCrZr AJ Cackett, HT Vo, JJH Lim, AJ Bushby, P Hosemann, CD Hardie Journal of Nuclear Materials 553, 153028, 2021 | 12 | 2021 |
| Structural integrity for DEMO: an opportunity to close the gap from materials science to engineering needs M Porton, BP Wynne, R Bamber, CD Hardie, M Kalsey Fusion Engineering and Design 109, 1247-1255, 2016 | 12 | 2016 |
