| Physics-based multiscale coupling for full core nuclear reactor simulation DR Gaston, CJ Permann, JW Peterson, AE Slaughter, D Andrš, Y Wang, ... Annals of Nuclear Energy 84, 45-54, 2015 | 374 | 2015 |
| Griffin software development plan C Lee, YS Jung, H Park, ER Shemon, J Ortensi, Y Wang, VM Labouré, ... Idaho National Lab.(INL), Idaho Falls, ID (United States); Argonne National …, 2021 | 93* | 2021 |
| Rattlesnake: A MOOSE-based multiphysics multischeme radiation transport application Y Wang, S Schunert, J Ortensi, V Laboure, M DeHart, Z Prince, F Kong, ... Nuclear Technology 207 (7), 1047-1072, 2021 | 84 | 2021 |
| Coupled multiphysics simulations of heat pipe microreactors using DireWolf C Matthews, V Laboure, M DeHart, J Hansel, D Andrs, Y Wang, J Ortensi, ... Nuclear Technology 207 (7), 1142-1162, 2021 | 77 | 2021 |
| Cumulative migration method for computing rigorous diffusion coefficients and transport cross sections from Monte Carlo Z Liu, K Smith, B Forget, J Ortensi Annals of Nuclear Energy 112, 507-516, 2018 | 62 | 2018 |
| A Newton solution for the Superhomogenization method: The PJFNK-SPH J Ortensi, Y Wang, A Laurier, S Schunert, A Hébert, M DeHart Annals of Nuclear Energy 111, 579-594, 2018 | 51 | 2018 |
| Multi-physics simulations of heat pipe micro reactor G Hu, R Hu, JM Kelly, J Ortensi Argonne National Lab.(ANL), Argonne, IL (United States), 2019 | 48 | 2019 |
| 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 | 39 | 2020 |
| Hybrid super homogenization and discontinuity factor method for continuous finite element diffusion V Labouré, Y Wang, J Ortensi, S Schunert, F Gleicher, M DeHart, ... Annals of Nuclear Energy 128, 443-454, 2019 | 38 | 2019 |
| Survey of dust production in pebble bed reactor cores JJ Cogliati, AM Ougouag, J Ortensi Nuclear engineering and design 241 (6), 2364-2369, 2011 | 36 | 2011 |
| A flexible nonlinear diffusion acceleration method for the SN transport equations discretized with discontinuous finite elements S Schunert, Y Wang, F Gleicher, J Ortensi, B Baker, V Laboure, C Wang, ... Journal of Computational Physics 338, 107-136, 2017 | 35 | 2017 |
| 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 |
| The coupling of the neutron transport application RATTLESNAKE to the fuels performance application bison FN Gleicher, J Ortensi International Conference on Reactor Physics (PHYSOR 2014), Kyoto, Japan, 2014 | 31 | 2014 |
| A cumulative migration method for computing rigorous transport cross sections and diffusion coefficients for LWR lattices with Monte Carlo Z Liu, K Smith, B Forget, J Ortensi Idaho National Lab.(INL), Idaho Falls, ID (United States), 2016 | 30 | 2016 |
| Control rod treatment for FEM based radiation transport methods S Schunert, Y Wang, J Ortensi, V Laboure, F Gleicher, M DeHart, ... Annals of Nuclear Energy 127, 293-302, 2019 | 29 | 2019 |
| Full core TREAT kinetics demonstration using Rattlesnake/BISON coupling within MAMMOTH J Ortensi, MD DeHart, FN Gleicher, Y Wang, S Schunert, AL Alberti, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2015 | 28 | 2015 |
| The coupling of the neutron transport application RATTLESNAKE to the nuclear fuels performance application BISON under the MOOSE framework FN Gleicher, RL Williamson, J Ortensi, Y Wang, BW Spencer, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2014 | 25 | 2014 |
| Deterministic modeling of the high temperature test reactor J Ortensi, JJ Cogliati, MA Pope, RM Ferrer, AM Ougouag Idaho National Lab.(INL), Idaho Falls, ID (United States), 2010 | 25 | 2010 |
| 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 | 23 | 2010 |
| Two-step neutronics calculations with Shift and Griffin for advanced reactor systems TM Pandya, F Bostelmann, M Jessee, J Ortensi Annals of Nuclear Energy 173, 109131, 2022 | 22 | 2022 |
