| Fabrication and microstructural analysis of UN-U3Si2 composites for accident tolerant fuel applications KD Johnson, AM Raftery, DA Lopes, J Wallenius Journal of Nuclear Materials 477, 18-23, 2016 | 100 | 2016 |
| Oxidation of accident tolerant fuel candidates K Johnson, V Ström, J Wallenius, DA Lopes Journal of Nuclear Science and Technology 54 (3), 280-286, 2017 | 79 | 2017 |
| Degradation of UN and UN–U3Si2 pellets in steam environment DA Lopes, S Uygur, K Johnson Journal of Nuclear Science and Technology 54 (4), 405-413, 2017 | 45 | 2017 |
| Grain growth in uranium nitride prepared by spark plasma sintering KD Johnson, DA Lopes Journal of Nuclear Materials 503, 75-80, 2018 | 34 | 2018 |
| Mechanical and thermal behaviour of U–Mo and U–Nb–Zr Alloys DA Lopes, TAG Restivo, AF Padilha Journal of nuclear materials 440 (1-3), 304-309, 2013 | 33 | 2013 |
| Stability of U5Si4 phase in U-Si system: Crystal structure prediction and phonon properties using first-principles calculations DA Lopes, V Kocevski, TL Wilson, EE Moore, TM Besmann Journal of Nuclear Materials 510, 331-336, 2018 | 30 | 2018 |
| Spark plasma sintering and microstructural analysis of pure and Mo doped U3Si2 pellets DA Lopes, A Benarosch, S Middleburgh, KD Johnson Journal of Nuclear Materials 496, 234-241, 2017 | 28 | 2017 |
| UN microspheres embedded in UO2 matrix: an innovative accident tolerant fuel DR Costa, M Hedberg, SC Middleburgh, J Wallenius, P Olsson, DA Lopes Journal of Nuclear Materials 540, 152355, 2020 | 27 | 2020 |
| Anisotropy in the thermal expansion of uranium silicide measured by neutron diffraction EG Obbard, KD Johnson, PA Burr, DA Lopes, DJ Gregg, KD Liss, ... Journal of Nuclear Materials 508, 516-520, 2018 | 26 | 2018 |
| Ab-initio study of C and O impurities in uranium nitride DA Lopes, A Claisse, P Olsson Journal of Nuclear Materials 478, 112-118, 2016 | 24 | 2016 |
| Oxidation of UN/U2N3-UO2 composites: an evaluation of UO2 as an oxidation barrier for the nitride phases DR Costa, M Hedberg, SC Middleburgh, J Wallenius, P Olsson, DA Lopes Journal of Nuclear Materials 544, 152700, 2021 | 23 | 2021 |
| Transport properties in dilute UN (X) solid solutions (X= Xe, Kr) A Claisse, T Schuler, DA Lopes, P Olsson Physical Review B 94 (17), 174302, 2016 | 21 | 2016 |
| Uranium nitride advanced fuel: an evaluation of the oxidation resistance of coated and doped grains Y Mishchenko, KD Johnson, D Jädernäs, J Wallenius, DA Lopes Journal of Nuclear Materials 556, 153249, 2021 | 17 | 2021 |
| Design and fabrication of UN composites: From first principles to pellet production Y Mishchenko, KD Johnson, J Wallenius, DA Lopes Journal of Nuclear Materials 553, 153047, 2021 | 17 | 2021 |
| Investigation of the on-site Coulomb correction and temperature dependence of the stability of U–Si phases using DFT+ U V Kocevski, DA Lopes, TM Besmann Journal of Nuclear Materials 524, 157-163, 2019 | 13 | 2019 |
| Effect of thermo-mechanical processing on microstructure and mechanical properties of U–Nb–Zr alloys: Part 1-U–6 wt.% Nb–6 wt.% Zr NWS Morais, DA Lopes, CG Schön Journal of Nuclear Materials 488, 173-180, 2017 | 12 | 2017 |
| Thermal cycling effect in U-10Mo/Zry-4 monolithic nuclear fuel DA Lopes, AJO Zimmermann, SL Silva, JRC Piqueira Journal of Nuclear Materials 473, 136-142, 2016 | 11 | 2016 |
| Understanding the interface interaction between U3Si2 fuel and SiC cladding V Kocevski, DA Lopes, AJ Claisse, TM Besmann Nature Communications 11 (1), 2621, 2020 | 10 | 2020 |
| Experimental system for studying temperature gradient-driven fracture of oxide nuclear fuel out of reactor S Patnaik, DA Lopes, TM Besmann, BW Spencer, TW Knight Review of Scientific Instruments 91 (3), 2020 | 10 | 2020 |
| Gamma-phase homogenization and texture in U–7.5 Nb–2.5 Zr (Mulberry) alloy DA Lopes, TAG Restivo, NB de Lima, AF Padilha Journal of Nuclear Materials 449 (1-3), 23-30, 2014 | 10 | 2014 |
