| 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 | 607 | 2015 |
| High-throughput synthesis of Mo-Nb-Ta-W high-entropy alloys via additive manufacturing M Moorehead, K Bertsch, M Niezgoda, C Parkin, M Elbakhshwan, ... Materials & Design 187, 108358, 2020 | 303 | 2020 |
| 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 | 214 | 2014 |
| ‘Low activation, refractory, high entropy alloys for nuclear applications’ A Kareer, JC Waite, B Li, A Couet, DEJ Armstrong, AJ Wilkinson Journal of Nuclear Materials 526, 151744, 2019 | 190 | 2019 |
| 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 | 151 | 2015 |
| Machine learning in nuclear materials research D Morgan, G Pilania, A Couet, BP Uberuaga, C Sun, J Li Current Opinion in Solid State and Materials Science 26 (2), 100975, 2022 | 130 | 2022 |
| High temperature, low neutron cross-section high-entropy alloys in the Nb-Ti-V-Zr system DJM King, STY Cheung, SA Humphry-Baker, C Parkin, A Couet, ... Acta Materialia 166, 435-446, 2019 | 121 | 2019 |
| Effect of alloying elements on hydrogen pickup in zirconium alloys A Couet, A Motta, R Comstock 17th International Symposium on Zirconium in the Nuclear Industry, 1-36, 2014 | 77 | 2014 |
| In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation C Parkin, M Moorehead, M Elbakhshwan, J Hu, WY Chen, M Li, L He, ... Acta Materialia 198, 85-99, 2020 | 64 | 2020 |
| Comprehensive investigation of the role of Nb on the oxidation kinetics of Zr-Nb alloys M Moorehead, Z Yu, L Borrel, J Hu, Z Cai, A Couet Corrosion Science 155, 173-181, 2019 | 61 | 2019 |
| Investigation of impurity driven corrosion behavior in molten 2LiF-BeF2 salt WH Doniger, C Falconer, M Elbakhshwan, K Britsch, A Couet, ... Corrosion Science 174, 108823, 2020 | 60 | 2020 |
| Microbeam X-ray absorption near-edge spectroscopy study of the oxidation of Fe and Nb in zirconium alloy oxide layers A Couet, AT Motta, B De Gabory, Z Cai Journal of Nuclear Materials 452 (1-3), 614-627, 2014 | 60 | 2014 |
| Integrated high‐throughput and machine learning methods to accelerate discovery of molten salt corrosion‐resistant alloys Y Wang, B Goh, P Nelaturu, T Duong, N Hassan, R David, M Moorehead, ... Advanced Science 9 (20), 2200370, 2022 | 58 | 2022 |
| In-situ electrochemical impedance spectroscopy measurements of zirconium alloy oxide conductivity: relationship to hydrogen pickup A Couet, AT Motta, A Ambard, D Livigni Corrosion Science 119, 1-13, 2017 | 58 | 2017 |
| Corrosion and thermal stability of CrMnFeNi high entropy alloy in molten FLiBe salt M Elbakhshwan, W Doniger, C Falconer, M Moorehead, C Parkin, ... Scientific reports 9 (1), 18993, 2019 | 53 | 2019 |
| Microstructure and microchemistry study of irradiation-induced precipitates in proton irradiated ZrNb alloys Z Yu, C Zhang, PM Voyles, L He, X Liu, K Nygren, A Couet Acta Materialia 178, 228-240, 2019 | 49 | 2019 |
| Irradiation-induced Nb redistribution of ZrNb alloy: An APT study Z Yu, A Couet, M Bachhav Journal of Nuclear Materials 516, 100-110, 2019 | 49 | 2019 |
| Effects of CO and O2 Impurities on Supercritical CO2 Corrosion of Alloy 625 J Mahaffey, A Schroeder, D Adam, A Brittan, M Anderson, A Couet, ... Metallurgical and Materials Transactions A 49 (8), 3703-3714, 2018 | 49 | 2018 |
| In situ X-ray and thermal imaging of refractory high entropy alloying during laser directed deposition H Wang, B Gould, M Moorehead, M Haddad, A Couet, SJ Wolff Journal of Materials Processing Technology 299, 117363, 2022 | 43 | 2022 |
| High-throughput ion irradiation of additively manufactured compositionally complex alloys M Moorehead, P Nelaturu, M Elbakhshwan, C Parkin, C Zhang, ... Journal of Nuclear Materials 547, 152782, 2021 | 43 | 2021 |
