| 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 | 106 | 2016 |
| Separate effects irradiation testing of miniature fuel specimens CM Petrie, JR Burns, AM Raftery, AT Nelson, KA Terrani Journal of Nuclear Materials 526, 151783, 2019 | 51 | 2019 |
| Integral LOCA fragmentation test on high-burnup fuel N Capps, Y Yan, A Raftery, Z Burns, T Smith, K Terrani, K Yueh, M Bales, ... Nuclear Engineering and Design 367, 110811, 2020 | 44 | 2020 |
| Onset conditions for flash sintering of UO2 AM Raftery, JGP da Silva, DD Byler, DA Andersson, BP Uberuaga, ... Journal of nuclear materials 493, 264-270, 2017 | 38 | 2017 |
| In situ X-ray characterization of uranium dioxide during flash sintering DJ Sprouster, E Kardoulaki, R Weidner, AM Raftery, M Elbakhshwan, ... Materialia 2, 176-182, 2018 | 20 | 2018 |
| Fabrication of UN-Mo CERMET nuclear fuel using advanced manufacturing techniques AM Raftery, RL Seibert, DR Brown, MP Trammell, AT Nelson, KA Terrani Nuclear Technology 207 (6), 815-824, 2021 | 16 | 2021 |
| Development of a characterization methodology for post-irradiation examination of miniature fuel specimens AM Raftery, RN Morris, KR Smith, GW Helmreich, CM Petrie, KA Terrani, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018 | 10 | 2018 |
| Properties and microstructure evolution of silicon nitride and zirconium nitride following Ni ion irradiation AJ Terricabras, L Wang, AM Raftery, AT Nelson, SJ Zinkle Journal of Nuclear Materials 563, 153643, 2022 | 6 | 2022 |
| Fabrication and characterization of UN-USix nuclear fuel AM Raftery | 6 | 2015 |
| Resolution capabilities for measurement of fuel swelling using tomography D Richardson, GW Helmreich, A Raftery, A Nelson Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019 | 4 | 2019 |
| In-cell Re-fabrication and Loss-of-coolant Accident (LOCA) Testing of High Burnup Commercial Spent Fuel AM Raftery, Y Yan, TS Smith, ZM Burns, KA Terrani, KD Linton Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2018 | 4 | 2018 |
| Tensile Testing of Irradiated Grade 92 Ferritic-Martensitic Steels at the IMET Hot Cell Facility AM Raftery, L Tan, H Sakasegawa, KD Linton Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2018 | 3 | 2018 |
| Completion of the Irradiation of Silicon Carbide Cladding Tube Specimens in the High Flux Isotope Reactor AM Raftery, CM Petrie, GJ Hirtz, Y Katoh, KD Linton Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2018 | 2 | 2018 |
| Corrigendum to “Integral LOCA fragmentation test on high-burnup fuel”[Nucl. Eng. Design (2020) 367 110811, ISN 0029-5493](S0029549320303058)(10.1016/j. nucengdes. 2020.110811) N Capps, Y Yan, A Raftery, Z Burns, T Smith, K Terrani, K Yueh, M Bales, ... Nuclear Engineering and Design 377, 111197, 2021 | 1 | 2021 |
| Integral LOCA fragmentation test on high-burnup fuel (vol 367, 110811, 2020) N Capps, Y Yan, A Raftery, Z Burns, T Smith, K Terrani, K Yueh, M Bales, ... NUCLEAR ENGINEERING AND DESIGN 377, 2021 | | 2021 |
| Lithography-based Ceramics Manufacturing Technologies A Nelson, A Raftery, C Cramer | | 2019 |
| Lithography-Based Ceramics Manufacturing Technologies CL Cramer, AM Raftery, AT Nelson Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2019 | | 2019 |
| Production and Characterization Package of Reference and Advanced Feedstock AM Raftery Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2019 | | 2019 |
| Resolution Capabilities for Measurement of Fuel Swelling using Tomography G Helmreich, A Nelson, M Richardson, A Raftery | | 2019 |
| Development of a characterization methodology for post-irradiation examination of miniature fuel specimens G Helmreich, C Petrie, A Nelson, K Terrani, K Smith, R Morris, A Raftery | | 2018 |
