| Understanding the reaction of nuclear graphite with molecular oxygen: Kinetics, transport, and structural evolution JJ Kane, CI Contescu, RE Smith, G Strydom, WE Windes Journal of Nuclear Materials 493, 343-367, 2017 | 88 | 2017 |
| The PBMR steady-state and coupled kinetics core thermal-hydraulics benchmark test problems F Reitsma, G Strydom, JBM De Haas, K Ivanov, B Tyobeka, R Mphahlele, ... Nuclear Engineering and Design 236 (5-6), 657-668, 2006 | 78 | 2006 |
| Comparison of the PHISICS/RELAP5-3D ring and block model results for phase I of the OECD/NEA MHTGR-350 benchmark G Strydom, AS Epiney, A Alfonsi, C Rabiti Nuclear Technology 193 (1), 15-35, 2016 | 46 | 2016 |
| Validation of the DALTON-THERMIX code system with transient analyses of the HTR-10 and application to the PBMR B Boer, D Lathouwers, JL Kloosterman, T Van Der Hagen, G Strydom Nuclear technology 170 (2), 306-321, 2010 | 45 | 2010 |
| Advanced demonstration and test reactor options study DA Petti, R Hill, J Gehin, HD Gougar, G Strydom, F Heidet, J Kinsey, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2017 | 43 | 2017 |
| A summary of the Department of Energy’s advanced demonstration and test reactor options study D Petti, R Hill, J Gehin, H Gougar, G Strydom, T O’Connor, F Heidet, ... Nuclear Technology 199 (2), 111-128, 2017 | 39 | 2017 |
| The US Department of Energy’s high temperature reactor research and development program–Progress as of 2019 HD Gougar, DA Petti, PA Demkowicz, WE Windes, G Strydom, JC Kinsey, ... Nuclear Engineering and Design 358, 110397, 2020 | 33 | 2020 |
| Prismatic coupled neutronics/thermal fluids transient benchmark of the MHTGR-350 MW core design: benchmark definition J Ortensi, M Pope, G Strydom draft version July 16, 2013 | 32 | 2013 |
| Role of nuclear grade graphite in controlling oxidation in modular HTGRs W Windes, G Strydom, J Kane, R Smith Idaho National Lab.(INL), Idaho Falls, ID (United States), 2014 | 30 | 2014 |
| IAEA Coordinated Research Project on HTGR Physics, Thermal-Hydraulics, and Depletion Uncertainty Analysis Prismatic HTGR Benchmark Specification: Phase II G Strydom Idaho National Lab.(INL), Idaho Falls, ID (United States), 2018 | 29 | 2018 |
| Nuclear data uncertainty and sensitivity analysis of the VHTRC benchmark using SCALE F Bostelmann, G Strydom Annals of Nuclear Energy 110, 317-329, 2017 | 28 | 2017 |
| The IAEA Coordinated Research Program on HTGR Reactor Physics, Thermal-Hydraulics and Depletion Uncertainty Analysis: Description of the Benchmark Test Cases and Phases F Reitsma, G Strydom, B Tyobeka, K Ivanov | 26 | 2012 |
| Fully Ceramic Microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Sensitivity of reactor behavior during design basis accidents to fuel properties and the … C Lu, T Koyanagi, Y Katoh, G Strydom, KA Terrani, NR Brown Nuclear Engineering and Design 345, 125-147, 2019 | 23 | 2019 |
| Prismatic Coupled Neutronics/Thermal Fluids Transient Benchmark of the MHTGR-350 MW Core Design: Benchmark Definition H Gougar, J Ortensi, MA Pope, S Sen, G Strydom, V Seker, B Collins, ... Idaho National Laboratory, 2010 | 22 | 2010 |
| TINTE uncertainty analysis of the maximum fuel temperature during a DLOFC event for the 400 MW Pebble Bed Modular Reactor G Strydom American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL …, 2004 | 22 | 2004 |
| PBMR coupled neutronics/thermal hydraulics transient benchmark the PBMR-400 core design F Reitsma, K Ivanov, T Downar, H de Hass, S Sen, G Strydom, ... NEA/NSC/DOC (2007) Draft-V07, OECD/NEA/NSC, 2007 | 21 | 2007 |
| PHISICS multi-group transport neutronic capabilities for RELAP5 A Epiney, C Rabiti, A Alfonsi, Y Wang, J Cogliati, G Strydom Proc. 2012 ICAPP 12, 24-28, 2012 | 19 | 2012 |
| Criticality calculations of the very high temperature reactor critical assembly benchmark with serpent and SCALE/KENO-VI F Bostelmann, HR Hammer, J Ortensi, G Strydom, K Velkov, W Zwermann Annals of Nuclear Energy 90, 343-352, 2016 | 17 | 2016 |
| High Temperature Gas-Cooled Test Reactor Point Design: Summary Report JW Sterbentz, PD Bayless, LO Nelson, HD Gougar, J Kinsey, G Strydom Idaho National Lab.(INL), Idaho Falls, ID (United States), 2016 | 17 | 2016 |
| Uncertainty and sensitivity analyses of a pebble bed HTGR loss of cooling event G Strydom Science and Technology of Nuclear Installations 2013 (1), 426356, 2013 | 17 | 2013 |
Andrea AlfonsiNuCube Energy Core Design Manager. Former USNC Nuclear Analysis Manager & INL RAVEN/PHISICS PI.在 nucube.energy 的电子邮件经过验证
Andrea AlfonsiNuCube Energy Core Design Manager. Former USNC Nuclear Analysis Manager & INL RAVEN/PHISICS PI.在 nucube.energy 的电子邮件经过验证