| MCNP® code version 6.3. 0 theory & user manual JA Kulesza, TR Adams, JC Armstrong, SR Bolding, FB Brown, JS Bull, ... Los Alamos National Lab.(LANL), Los Alamos, NM (United States), 2022 | 68 | 2022 |
| 3-D anisotropic neutron diffusion in optically thick media with optically thin channels TJ Trahan, EW Larsen | 16 | 2011 |
| Mpact theory manual B Collins, T Downar, J Gehin, A Godfrey, A Graham, D Jabaay, B Kelley, ... Technical Report CASL-U-2015-0078-000, Consortium for Advanced Simulation of …, 2015 | 15 | 2015 |
| An Asymptotic, Homogenized, Anisotropic, Multigroup Diffusion Approximation to the Neutron Transport Equation. TJ Trahan | 14 | 2014 |
| 2-D anisotropic diffusion in optically thin channels EW Larsen, TJ Trahan Transactions of the American Nuclear Society 101, 387-389, 2009 | 12 | 2009 |
| An asymptotic homogenized neutron diffusion approximation. II. Numerical comparisons TJ Trahan, EW Larsen American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park …, 2012 | 10 | 2012 |
| A quasi-static Monte Carlo algorithm for the simulation of sub-prompt critical transients TJ Trahan Annals of Nuclear Energy 127, 257-267, 2019 | 9 | 2019 |
| MCNP® Code Version 6.3. 0 Theory & User Manual. Los Alamos National Laboratory Tech. Rep JA Kulesza, TR Adams, JC Armstrong, SR Bolding, FB Brown, JS Bull, ... LA-UR-22-30006, Rev. 1. Los Alamos, NM, USA, 2022 | 8 | 2022 |
| Analytic treatment of source photon emission times to reduce noise in implicit Monte Carlo calculations TJ Trahan, NA Gentile Transport Theory and Statistical Physics 41 (3-4), 265-283, 2012 | 7 | 2012 |
| A Monte Carlo Algorithm for Fission Chain Analysis of Dynamic Stochastic Systems TJ Trahan, S Nolen, T Adams, J Sweezy Trans. Am. Nucl. Soc 113, 661, 2015 | 6 | 2015 |
| Galerkin-quadratures for the SN method in 2D cartesian geometries and application to forward-peaked scattering particle transport problems T Trahan, J Ragusa, J Morel | 6 | 2009 |
| MPACT Theory Manual, Version 2.2. 0 T Downar, BS Collins, JC Gehin, AT Godfrey, D Jabaay, BW Kelley, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). Consortium for …, 2016 | 5 | 2016 |
| Asymptotic, multigroup flux reconstruction and consistent discontinuity factors TJ Trahan, EW Larsen Journal of Nuclear Science and Technology 52 (7-8), 917-931, 2015 | 5 | 2015 |
| MPACT Standard Input User s Manual, Version 2.2. 0 BS Collins, T Downar, A Fitzgerald, JC Gehin, AT Godfrey, A Graham, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). Consortium for …, 2016 | 3 | 2016 |
| Verification of solid body geometries in MCATK T Trahan, J Sweezy, J Giron Physics of Reactors (PHYSOR), 1-5, 2016 | 3 | 2016 |
| Monte Carlo Calculation of Moments of the Neutron Number and Fission Number for Stochastic Systems in MCATK TJ Trahan Proc. M&C 2017, 16-20, 2017 | 2 | 2017 |
| An Overview of the Monte Carlo Application ToolKit (MCATK) TJ Trahan Los Alamos National Laboratory (LANL), Los Alamos, NM (United States), 2016 | 2 | 2016 |
| Multiphysics simulation of two criticality accident excursions in Lady Godiva using MCATK TJ Trahan, RH Kimpland, WL Myers, S Dossa | 1 | 2019 |
| Region-Specific Monte Carlo Analysis of Stochastic Systems TJ Trahan Trans. Am. Nucl. Soc 119, 2018 | 1 | 2018 |
| MPACT A Graham, A Berkovec, A Hoffman, A Nelson, A Fitzgerald, A Gerlach, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018 | 1 | 2018 |
