| Radiation effects in crystalline ceramics for the immobilization of high-level nuclear waste and plutonium WJ Weber, RC Ewing, CRA Catlow, TD De La Rubia, LW Hobbs, ... Journal of Materials Research 13 (6), 1434-1484, 1998 | 1059 | 1998 |
| Corrosion of zirconium alloys used for nuclear fuel cladding AT Motta, A Couet, RJ Comstock Annual Review of Materials Research 45 (1), 311-343, 2015 | 484 | 2015 |
| Structure of zirconium alloy oxides formed in pure water studied with synchrotron radiation and optical microscopy: relation to corrosion rate A Yilmazbayhan, AT Motta, RJ Comstock, GP Sabol, B Lai, Z Cai Journal of Nuclear Materials 324 (1), 6-22, 2004 | 343 | 2004 |
| Transmission electron microscopy examination of oxide layers formed on Zr alloys A Yilmazbayhan, E Breval, AT Motta, RJ Comstock Journal of Nuclear Materials 349 (3), 265-281, 2006 | 330 | 2006 |
| Zirconium alloys in nuclear applications C Lemaignan, AT Motta Materials science and technology, 2006 | 314 | 2006 |
| Hydrogen in zirconium alloys: A review AT Motta, L Capolungo, LQ Chen, MN Cinbiz, MR Daymond, DA Koss, ... Journal of Nuclear Materials 518, 440-460, 2019 | 296 | 2019 |
| A thermal spike model of grain growth under irradiation D Kaoumi, AT Motta, RC Birtcher Journal of Applied Physics 104 (7), 2008 | 245 | 2008 |
| 5.03 corrosion of zirconium alloys TR Allen, RJM Konings, AT Motta Comprehensive nuclear materials 5, 49-68, 2012 | 243 | 2012 |
| Multilayer (TiN, TiAlN) ceramic coatings for nuclear fuel cladding E Alat, AT Motta, RJ Comstock, JM Partezana, DE Wolfe Journal of Nuclear Materials 478, 236-244, 2016 | 230 | 2016 |
| Zirconium alloys for supercritical water reactor applications: Challenges and possibilities AT Motta, A Yilmazbayhan, MJG da Silva, RJ Comstock, GS Was, ... Journal of Nuclear Materials 371 (1-3), 61-75, 2007 | 208 | 2007 |
| Hydrogen pickup measurements in zirconium alloys: Relation to oxidation kinetics A Couet, AT Motta, RJ Comstock Journal of Nuclear Materials 451 (1-3), 1-13, 2014 | 191 | 2014 |
| Oxidation behavior of ferritic–martensitic and ODS steels in supercritical water J Bischoff, AT Motta Journal of Nuclear Materials 424 (1-3), 261-276, 2012 | 177 | 2012 |
| In situ study of hydride precipitation kinetics and re-orientation in Zircaloy using synchrotron radiation KB Colas, AT Motta, JD Almer, MR Daymond, M Kerr, AD Banchik, ... Acta Materialia 58 (20), 6575-6583, 2010 | 163 | 2010 |
| Identification and quantification of hydride phases in Zircaloy-4 cladding using synchrotron X-ray diffraction RS Daum, YS Chu, AT Motta Journal of Nuclear Materials 392 (3), 453-463, 2009 | 160 | 2009 |
| Hydride formation in zirconium alloys AT Motta, LQ Chen Jom 64, 1403-1408, 2012 | 149 | 2012 |
| Amorphization of intermetallic compounds under irradiation—A review AT Motta Journal of Nuclear Materials 244 (3), 227-250, 1997 | 147 | 1997 |
| Precipitate evolution in the Zircaloy-4 oxide layer D Pecheur, F Lefebvre, AT Motta, C Lemaignan, JF Wadier Journal of Nuclear Materials 189 (3), 318-332, 1992 | 147 | 1992 |
| The coupled current charge compensation model for zirconium alloy fuel cladding oxidation: I. Parabolic oxidation of zirconium alloys A Couet, AT Motta, A Ambard Corrosion Science 100, 73-84, 2015 | 135 | 2015 |
| Ceramic coating for corrosion (c3) resistance of nuclear fuel cladding E Alat, AT Motta, RJ Comstock, JM Partezana, DE Wolfe Surface and coatings technology 281, 133-143, 2015 | 133 | 2015 |
| Failure of Zircaloy cladding under transverse plane-strain deformation TM Link, DA Koss, AT Motta Nuclear Engineering and Design 186 (3), 379-394, 1998 | 129 | 1998 |
