| OpenMC: A state-of-the-art Monte Carlo code for research and development PK Romano, NE Horelik, BR Herman, AG Nelson, B Forget, K Smith Annals of Nuclear Energy 82, 90-97, 2015 | 757 | 2015 |
| Assembly of high-areal-density deuterium-tritium fuel from indirectly driven cryogenic implosions AJ Mackinnon, JL Kline, SN Dixit, SH Glenzer, MJ Edwards, DA Callahan, ... Physical Review Letters 108 (21), 215005, 2012 | 69 | 2012 |
| Multigroup cross-section generation with the OpenMC Monte Carlo particle transport code W Boyd, A Nelson, PK Romano, S Shaner, B Forget, K Smith Nuclear Technology, 2019 | 38 | 2019 |
| Pityriasis lichenoides et varioliformis acuta in HIV‐1+ patients: a marker of early stage disease KJ Smith, A Nelson, H Skelton, J Yeager, KR Wagner, ... International journal of dermatology 36 (2), 104-109, 1997 | 35 | 1997 |
| Monte Carlo methods for neutron transport on graphics processing units using CUDA AG Nelson | 25 | 2009 |
| Improved Convergence Rate of Multi-Group Scattering Moment Tallies for Monte Carlo Neutron Transport Codes A Nelson University of Michigan, 2014 | 13 | 2014 |
| Preservation of allergic contact dermatitis to poison ivy (urushiol) in late HIV disease KJ Smith, HG Skelton, A Nelson, KF Wagner, H BE Jr Dermatology 195 (2), 145-149, 1997 | 13 | 1997 |
| The effect of the flux separability approximation on multigroup neutron transport AG Nelson, W Boyd, PK Romano Journal of Nuclear Engineering 2 (1), 86-96, 2021 | 9 | 2021 |
| Verification of the DIF3D Software to Support Fast Reactor Analysis AG Nelson, MA Smith Argonne National Lab.(ANL), Argonne, IL (United States), 2022 | 8 | 2022 |
| Personality and work performance: Some evidence from small and medium-sized firms A Nelson, IT Robertson, L Walley, M Smith Occupational Psychologist 12, 28-36, 1999 | 7 | 1999 |
| User Guide to the Advanced Dimensional Depletion for Engineering of Reactors (ADDER) Software (V. 1.0) AG Nelson Argonne National Lab.(ANL), Argonne, IL (United States), 2021 | 3 | 2021 |
| Molten salt reactor depletion techniques in the ADDER reactor depletion and fuel management analysis core AG Nelson, MG Jarrett, GJY Chee Proceedings of the international conference on mathematics and computational …, 2021 | 3 | 2021 |
| Impact of Nuclear Data Libraries on Predicted Fast Reactor Performance AG Nelson, KM Ramey, F Heidet EPJ Web of Conferences 247, 09026, 2021 | 3 | 2021 |
| Incorporation of a multigroup transport capability in the OpenMC Monte Carlo Particle transport code AG Nelson, S Shaner, W Boyd, PK Romano Transactions of the American Nuclear Society: Washington, DC, USA 117, 679-681, 2017 | 3 | 2017 |
| Performance of HALEU and HEU-fueled nuclear thermal propulsion reactors AG Nelson, AA Kasam-Griffith, MI Atz, F Heidet Argonne National Lab.(ANL), Argonne, IL (United States), 2021 | 2 | 2021 |
| The ADDER Software for Reactor Depletion and Fuel Management Analysis AG Nelson, JA Stillman, F Heidet, EH Wilson American Nuclear Society Winter Meeting (accepted), Virtual, 2020 | 2 | 2020 |
| 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 | 2 | 2016 |
| Improved convergence of Monte Carlo generated multi-group scattering moments AG Nelson, WR Martin Int. Conf. Mathematics and Computational Methods Applied to Nuclear Science …, 2013 | 2 | 2013 |
| Methods for processing and use of thermal neutron scattering data in OpenMC PK Romano, AG Nelson EPJ Web of Conferences 284, 17011, 2023 | 1 | 2023 |
| Uncertainty Quantification Approach for the Versatile Test Reactor Core Design AG Nelson, N Martin, A Kasam-Griffith, Z Xu, F Heidet Nuclear Science and Engineering 196 (sup1), 63-70, 2022 | 1 | 2022 |
