| Analysis of population control techniques for time-dependent and eigenvalue Monte Carlo neutron transport calculations I Variansyah, RG McClarren Nuclear Science and Engineering 196 (11), 1280-1305, 2022 | 15* | 2022 |
| Multigroup constant calculation with static α-eigenvalue Monte Carlo for time-dependent neutron transport simulations I Variansyah, BR Betzler, WR Martin Nuclear Science and Engineering 194 (11), 1025-1043, 2020 | 13 | 2020 |
| Variable dynamic mode decomposition for estimating time eigenvalues in nuclear systems E Smith, I Variansyah, R McClarren Nuclear Science and Engineering 197 (8), 1769-1778, 2023 | 11 | 2023 |
| Development of MC/DC: a performant, scalable, and portable Python-based Monte Carlo neutron transport code I Variansyah, JP Morgan, J Northrop, KE Niemeyer, RG McClarren arXiv preprint arXiv:2305.07636, 2023 | 11 | 2023 |
| Metaheuristic Optimization Tool I Variansyah, JW Bae, BR Betzler, G Ilas Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2020 | 7 | 2020 |
| A Quasi–Monte Carlo Method With Krylov Linear Solvers for Multigroup Neutron Transport Simulations S Pasmann, I Variansyah, CT Kelley, R McClarren Nuclear Science and Engineering 197 (6), 1159-1173, 2023 | 6 | 2023 |
| An effective initial particle sampling technique for Monte Carlo reactor transient simulations I Variansyah, RG McClarren arXiv preprint arXiv:2305.07646, 2023 | 5 | 2023 |
| iQMC: Iterative Quasi-Monte Carlo for k-Eigenvalue Neutron Transport Simulations S Pasmann, I Variansyah, CT Kelley, RG McClarren arXiv preprint arXiv:2306.11600, 2023 | 3 | 2023 |
| High-fidelity treatment for object movement in time-dependent Monte Carlo transport simulations I Variansyah, RG McClarren arXiv preprint arXiv:2305.07641, 2023 | 3 | 2023 |
| Performance of Population Control Techniques in Monte Carlo Reactor Criticality Simulations I Variansyah, RG McClarren Proc. PHYSOR, 2022 | 3 | 2022 |
| A Robust Second-Order Multiple Balance Method for Time-Dependent Neutron Transport Simulations I Variansyah, EW Larsen, WR Martin EPJ Web of Conferences 247, 03024, 2021 | 3 | 2021 |
| α-weighted Transition Rate Matrix Method I Variansyah, BR Betzler, WR Martin Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2019 | 3 | 2019 |
| Reducing Spatial Discretization Error with Linear Discontinuous Source Tilting in Iterative Quasi-Monte Carlo for Neutron Transport S Pasmann, I Variansyah, CT Kelley, RG McClarren arXiv preprint arXiv:2306.14877, 2023 | 2 | 2023 |
| A metaheuristic optimization tool for high flux isotope reactor low-enriched uranium core design I Variansyah, B Betzler, D Chandler, G Ilas, WR Martin Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2019 | 2 | 2019 |
| Mitigating Spatial Error in the Iterative Quasi–Monte Carlo (iQMC) Method for Neutron Transport Simulations with Linear Discontinuous Source Tilting and Effective Scattering … S Pasmann, I Variansyah, CT Kelley, RG McClarren Nuclear Science and Engineering, 1-16, 2024 | 1 | 2024 |
| An Alternative to Stride-Based RNG for Monte Carlo Transport BS Cuneo, I Variansyah arXiv preprint arXiv:2403.06362, 2024 | 1 | 2024 |
| Monte Carlo/Dynamic Code (MC/DC): An accelerated Python package for fully transient neutron transport and rapid methods development JP Morgan, I Variansyah, SL Pasmann, KB Clements, B Cuneo, A Mote, ... Journal of Open Source Software 9 (96), 6415, 2024 | | 2024 |
| Development of Machine Learning Model for Neutron Clustering Classification in Monte Carlo Criticality Simulation AR Hakim, I Variansyah, DA Fynan Canadian Nuclear Society, American Nuclear Society, 2023 | | 2023 |
| Exploring One-Cell Inversion Method for Transient Transport on GPU JP Morgan, I Variansyah, TS Palmer, KE Niemeyer arXiv preprint arXiv:2305.13555, 2023 | | 2023 |
| A Robust Second-Order Multiple Balance Method and Alpha-Weighted Multigroup Constants for Time-Dependent Nuclear Reactor Simulations I Variansyah | | 2021 |
