Arthur T Motta
Cited by
Cited by
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
Corrosion of zirconium alloys used for nuclear fuel cladding
AT Motta, A Couet, RJ Comstock
Annual Review of Materials Research 45, 311-343, 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
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
Zirconium alloys in nuclear applications
C Lemaignan, AT Motta
Materials science and technology, 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
A thermal spike model of grain growth under irradiation
D Kaoumi, AT Motta, RC Birtcher
Journal of Applied Physics 104 (7), 2008
5.03 corrosion of zirconium alloys
TR Allen, RJM Konings, AT Motta
Comprehensive nuclear materials 5, 49-68, 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
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
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
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
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
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
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
Hydride formation in zirconium alloys
AT Motta, LQ Chen
Jom 64, 1403-1408, 2012
Amorphization of intermetallic compounds under irradiation—A review
AT Motta
Journal of Nuclear Materials 244 (3), 227-250, 1997
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
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
Failure of Zircaloy cladding under transverse plane-strain deformation
TM Link, DA Koss, AT Motta
Nuclear Engineering and Design 186 (3), 379-394, 1998
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