| Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT B Collins, S Stimpson, BW Kelley, MTH Young, B Kochunas, A Graham, ... Journal of Computational Physics 326, 612-628, 2016 | 194 | 2016 |
| Overview of development and design of MPACT: Michigan parallel characteristics transport code B Kochunas, B Collins, D Jabaay, TJ Downar, WR Martin American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL …, 2013 | 169 | 2013 |
| VERA core simulator methodology for pressurized water reactor cycle depletion B Kochunas, B Collins, S Stimpson, R Salko, D Jabaay, A Graham, Y Liu, ... Nuclear Science and Engineering 185 (1), 217-231, 2017 | 125 | 2017 |
| An optimally diffusive Coarse Mesh Finite Difference method to accelerate neutron transport calculations A Zhu, M Jarrett, Y Xu, B Kochunas, E Larsen, T Downar Annals of Nuclear Energy 95, 116-124, 2016 | 105 | 2016 |
| Digital twin concepts with uncertainty for nuclear power applications B Kochunas, X Huan Energies 14 (14), 4235, 2021 | 74 | 2021 |
| Analysis of stabilization techniques for CMFD acceleration of neutron transport problems M Jarrett, B Kochunas, A Zhu, T Downar Nuclear Science and Engineering 184 (2), 208-227, 2016 | 68 | 2016 |
| A Hybrid Parallel Algorithm for the 3-D Method of Characteristics Solution of the Boltzmann Transport Equation on High Performance Compute Clusters. BM Kochunas | 64 | 2013 |
| VERA Benchmarking Results for Watts Bar Nuclear Plant Unit 1 Cycles 1-12 A Godfrey, B Collins, KS Kim, J Powers, R Salko, S Stimpson, ... Physics of Reactors 2016: Unifying Theory and Experiments in the 21st …, 2016 | 54 | 2016 |
| Transient analysis of C5G7-TD benchmark with MPACT Q Shen, Y Wang, D Jabaay, B Kochunas, T Downar Annals of Nuclear Energy 125, 107-120, 2019 | 53 | 2019 |
| High fidelity modeling of pellet-clad interaction using the CASL virtual environment for reactor applications KT Clarno, RP Pawlowski, RO Montgomery, TM Evans, BS Collins, ... Mathematics and Computations, Supercomputing in Nuclear Applications and …, 2015 | 35 | 2015 |
| VERA core simulator methodology for PWR cycle depletion B Kochunas, BS Collins, D Jabaay, KS Kim, A Graham, S Stimpson, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). Oak Ridge …, 2015 | 32 | 2015 |
| Demonstration of neutronics coupled to thermal-hydraulics for a full-core problem using cobra-tf/mpact B Kochunas, D Jabaay, B Collins, T Downar CASL Document CASL-U-2014-0051-000, 2014 | 31 | 2014 |
| Coupled computational fluid dynamics and MOC neutronic simulations of Westinghouse PWR fuel assemblies with grid spacers J Yan, B Kochunas, M Hursin, T Downar, Z Karoutas, E Baglietto | 29 | 2011 |
| Improvement of transport-corrected scattering stability and performance using a Jacobi inscatter algorithm for 2D-MOC S Stimpson, B Collins, B Kochunas Annals of Nuclear Energy 105, 1-10, 2017 | 28 | 2017 |
| A multilevel in space and energy solver for 3-D multigroup diffusion and coarse-mesh finite difference eigenvalue problems BC Yee, B Kochunas, EW Larsen Nuclear Science and Engineering 193 (7), 722-745, 2019 | 27 | 2019 |
| Parallel 3-D method of characteristics in MPACT B Kochunas, TJ Dovvnar, Z Liu American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL …, 2013 | 27 | 2013 |
| Space-dependent wielandt shifts for multigroup diffusion eigenvalue problems BC Yee, B Kochunas, EW Larsen, Y Xu Nuclear science and engineering 188 (2), 140-159, 2017 | 23 | 2017 |
| A multilevel in space and energy solver for multigroup diffusion eigenvalue problems BC Yee, B Kochunas, EW Larsen Nuclear Engineering and Technology 49 (6), 1125-1134, 2017 | 23 | 2017 |
| Validation and Verification of the MPACT Code T Downar, B Kochunas, SM Bowman Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2016 | 22 | 2016 |
| Analysis of the core power response during a PWR rod ejection transient using the PARCS nodal code and the DeCART MOC code M Hursin, TJ Downar, B Kochunas Nuclear science and engineering 170 (2), 151-167, 2012 | 22 | 2012 |
