| Ag diffusion in cubic silicon carbide D Shrader, SM Khalil, T Gerczak, TR Allen, AJ Heim, I Szlufarska, ... Journal of Nuclear Materials 408 (3), 257-271, 2011 | 113 | 2011 |
| Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation KA Terrani, Y Yang, YJ Kim, R Rebak, HM Meyer III, TJ Gerczak Journal of Nuclear Materials 465, 488-498, 2015 | 91 | 2015 |
| Detection and analysis of particles with failed SiC in AGR-1 fuel compacts JD Hunn, CA Baldwin, TJ Gerczak, FC Montgomery, RN Morris, CM Silva, ... Nuclear Engineering and Design 306, 36-46, 2016 | 88 | 2016 |
| AGR-1 post irradiation examination final report PA Demkowicz Idaho National Lab.(INL), Idaho Falls, ID (United States), 2015 | 76 | 2015 |
| Irradiation performance of AGR-1 high temperature reactor fuel PA Demkowicz, JD Hunn, SA Ploger, RN Morris, CA Baldwin, JM Harp, ... Nuclear Engineering and Design 306, 2-13, 2016 | 69 | 2016 |
| Restructuring in high burnup UO2 studied using modern electron microscopy TJ Gerczak, CM Parish, PD Edmondson, CA Baldwin, KA Terrani Journal of Nuclear Materials 509, 245-259, 2018 | 58 | 2018 |
| Initial examination of fuel compacts and TRISO particles from the US AGR-2 irradiation test JD Hunn, CA Baldwin, FC Montgomery, TJ Gerczak, RN Morris, ... Nuclear Engineering and Design 329, 89-101, 2018 | 55 | 2018 |
| Initial results from safety testing of US AGR-2 irradiation test fuel RN Morris, JD Hunn, CA Baldwin, FC Montgomery, TJ Gerczak, ... Nuclear Engineering and Design 329, 124-133, 2018 | 44 | 2018 |
| SiC layer microstructure in AGR-1 and AGR-2 TRISO fuel particles and the influence of its variation on the effective diffusion of key fission products TJ Gerczak, JD Hunn, RA Lowden, TR Allen Journal of Nuclear Materials 480, 257-270, 2016 | 42 | 2016 |
| Observations of Ag diffusion in ion implanted SiC TJ Gerczak, B Leng, K Sridharan, JL Hunter Jr, AJ Giordani, TR Allen Journal of Nuclear Materials 461, 314-324, 2015 | 29 | 2015 |
| Effect of carbon ion irradiation on Ag diffusion in SiC B Leng, H Ko, TJ Gerczak, J Deng, AJ Giordani, JL Hunter Jr, D Morgan, ... Journal of Nuclear Materials 471, 220-232, 2016 | 21 | 2016 |
| Post-irradiation examination and safety testing of US AGR-2 irradiation test compacts JD Hunn, RN Morris, FC Montgomery, TJ Gerczak, DJ Skitt, CA Baldwin, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018 | 20 | 2018 |
| PIE on safety-tested AGR-1 Compact 4-2-2 JD Hunn, RN Morris, CA Baldwin, FC Montgomery, TJ Gerczak ORNL/TM-2015/033, Oak Ridge National Laboratory, 2015 | 18 | 2015 |
| AGR-2 TRISO Fuel Post-Irradiation Examination Final Report JD Stempien, RN Morris, TJ Gerczak, PA Demkowicz Idaho National Lab.(INL), Idaho Falls, ID (United States), 2021 | 17 | 2021 |
| Analysis of fission product distribution and composition in the TRISO layers of AGR-2 fuel TJ Gerczak, JD Hunn, RN Morris, FC Montgomery, DJ Skitt, CA Baldwin, ... Nuclear Engineering and Design 364, 110656, 2020 | 17 | 2020 |
| AGR-1 Irradiated Compact 4-4-2 PIE Report: Evaluation of As-Irradiated Fuel Performance with Leach Burn Leach, IMGA, Materialography, and X-ray Tomography JD Hunn, RN Morris, CA Baldwin, FC Montgomery, CM Silva, TJ Gerczak ORNL/TM-2013/236, Revision 0. Oak Ridge, Tennessee: Oak Ridge National …, 2013 | 17 | 2013 |
| Characterization of PyC/SiC interfaces with FIB-SEM tomography JD Arregui-Mena, RL Seibert, TJ Gerczak Journal of Nuclear Materials 545, 152736, 2021 | 15 | 2021 |
| Fluoride-Salt-Cooled High Temperature Reactor (FHR) Materials, Fuels and Components White Paper G Cao, T Gerczak, B Kelleher, G Zheng, D Carpenter, AT Cisneros, ... Department of Nuclear Engineering, UC Berkeley, 2013 | 15 | 2013 |
| AGR-1 Irradiated Compact 6-1-1 PIE Report: Evaluation of As-Irradiated Fuel Performance Using Leach Burn Leach, IMGA, Materialography, and X-ray Tomography JD Hunn, RN Morris, C Baldwin, FC Montgomery, GW Silva, TJ Gerczak Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2012 | 14 | 2012 |
| Electron microscopy study of Pd, Ag, and Cs in carbon areas in the locally corroded SiC layer in a neutron-irradiated TRISO fuel particle H Wen, IJ van Rooyen, JD Hunn, TJ Gerczak Journal of the European Ceramic Society 38 (12), 4173-4188, 2018 | 13 | 2018 |
