| Development of a microstructural grand potential-based sintering model I Greenquist, MR Tonks, LK Aagesen, Y Zhang Computational Materials Science 172, 109288, 2020 | 47 | 2020 |
| Review of sintering and densification in nuclear fuels: Physical mechanisms, experimental results, and computational models I Greenquist, MR Tonks, Y Zhang Journal of Nuclear Materials 507, 381-395, 2018 | 25 | 2018 |
| Grand potential sintering simulations of doped UO2 accident-tolerant fuel concepts I Greenquist, M Tonks, M Cooper, D Andersson, Y Zhang Journal of Nuclear Materials 532, 152052, 2020 | 24 | 2020 |
| Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 1: Overview and code coupling strategies I Greenquist, A Wysocki, J Hirschhorn, N Capps Annals of Nuclear Energy 191, 109913, 2023 | 10 | 2023 |
| Metallic fuel performance benchmarks for versatile test reactor applications JA Hirschhorn, JJ Powers, I Greenquist, RT Sweet, J Hu, DL Porter, ... Nuclear Science and Engineering 196 (sup1), 123-147, 2022 | 7 | 2022 |
| Development of a U-19Pu-10Zr fuel performance benchmark case based on the IFR-1 experiment I Greenquist, KM Cunningham, J Hu, JJ Powers, DC Crawford Journal of Nuclear Materials 553, 152997, 2021 | 7 | 2021 |
| A Metallic Fuel Performance Benchmark Problem Based on the IFR-1 Experiment I Greenquist, KM Cunningham, J Hu, JJ Powers Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2020 | 7 | 2020 |
| Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 3: Thermal hydraulic evaluation of large break LOCA under high-burnup conditions A Wysocki, J Hirschhorn, I Greenquist, N Capps Annals of Nuclear Energy 192, 109951, 2023 | 6 | 2023 |
| 25-Pin metallic fuel performance benchmark case based on the EBR-II X430 experiments series I Greenquist, JJ Powers Journal of Nuclear Materials 556, 153211, 2021 | 6 | 2021 |
| Research Needs for Uranium-Zirconium-Based Metallic Fuels A Aitkaliyeva, M Tonks, J Hirschhorn, J Powers, I Greenquist, B Beeler Idaho National Lab.(INL), Idaho Falls, ID (United States), 2020 | 6 | 2020 |
| Metallic Fuel Benchmark Simulations Based on the X430 Experiments IT Greenquist, JJ Powers Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2020 | 5 | 2020 |
| Sensitivity and uncertainty of the IFR-1 BISON benchmark I Greenquist, JJ Powers Progress in Nuclear Energy 152, 104361, 2022 | 4 | 2022 |
| Analysis of the impact of fuel microstructure on irradiation-enhanced densification using grand potential simulations I Greenquist, M Tonks, Y Zhang Annals of Nuclear Energy 151, 107858, 2021 | 4 | 2021 |
| Multiphysics analysis of fuel Fragmentation, Relocation, and dispersal Susceptibility–Part 2: High-Burnup Steady-State operating and fuel performance conditions J Hirschhorn, I Greenquist, A Wysocki, N Capps Annals of Nuclear Energy 192, 109952, 2023 | 3 | 2023 |
| Assessment of the Effect of Prototypic High-Burnup Operating Conditions of Fuel Fragmentation, Relocation, and Dispersal Susceptibility N Capps, J Hirschhorn, A Wysocki, I Greenquist ORNL, Oak Ridge, 2022 | 3 | 2022 |
| Coupled Neutronics, Thermal Hydraulics, and Fuel Performance Simulations of a Natural Circulation Based SMR R Sweet, I Greenquist, A Graham, R Trotta, C Lietwiler, F Odeh Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2023 | 2 | 2023 |
| Multiphysics Analysis of Fuel Fragmentation, Relocation, and Dispersal Susceptibility–Part 2: High-Burnup Steady-State Operating and Fuel Performance Conditions N Capps, J Hirschhorn, I Greenquist, A Wysocki Relocation, and Dispersal Susceptibility–Part 2, 2023 | 2 | 2023 |
| Development of Microreactor Automated Control System (MACS): Surrogate Plant-level Modeling and Control Algorithms Integration W Williams, P Ramuhalli, I Greenquist Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2023 | 1 | 2023 |
| Accelerated fission rate irradiation design, pre-irradiation characterization, and adaptation of conventional PIE methods for U-10Mo and U-17Mo P Doyle, C Massey, D Richardson, I Greenquist, R Seibert, G Helmreich, ... Frontiers in Nuclear Engineering 1, 1054288, 2023 | 1 | 2023 |
| Coupled Neutronic and Thermal Hydraulic Analysis of a Natural Circulation Based Small Modular Reactor (SMR) Using VERA-CS AM Graham, JD Rader, AT Godfrey, RT Sweet, IT Greenquist Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2022 | 1 | 2022 |
Michael R TonksMaterials Science and Engineering, University of FloridaVerified email at ufl.edu
