| The OpenMOC method of characteristics neutral particle transport code W Boyd, S Shaner, L Li, B Forget, K Smith Annals of Nuclear Energy 68, 43-52, 2014 | 189 | 2014 |
| 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 |
| An analysis of condensation errors in multi-group cross section generation for fine-mesh neutron transport calculations W Boyd, N Gibson, B Forget, K Smith Annals of Nuclear Energy 112, 267-276, 2018 | 26 | 2018 |
| Accuracy and performance of 3D MOC for full-core PWR problems G Gunow, S Shaner, W Boyd, B Forget, K Smith | 26 | 2017 |
| A massively parallel method of characteristic neutral particle transport code for GPUs WR Boyd, K Smith, B Forget American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL …, 2013 | 23 | 2013 |
| Massively parallel algorithms for method of characteristics neutral particle transport on shared memory computer architectures WRD Boyd III Massachusetts Institute of Technology, 2014 | 18 | 2014 |
| Parallel performance results for the OpenMOC neutron transport code on multicore platforms W Boyd, A Siegel, S He, B Forget, K Smith The International Journal of High Performance Computing Applications 30 (3 …, 2016 | 16 | 2016 |
| Parallel performance results for the OpenMOC method of characteristics code on multi-core platforms W Boyd, K Smith, B Forget, A Siegel | 10 | 2015 |
| 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 |
| A single-step framework to generate spatially self-shielded multi-group cross sections from Monte Carlo transport simulations W Boyd, B Forget, K Smith Annals of Nuclear Energy 125, 261-271, 2019 | 7 | 2019 |
| A memory efficient algorithm for classifying unique regions in constructive solid geometries D Lax, W Boyd, N Horelik, B Forget, K Smith | 7 | 2015 |
| Equipping openmc for the big data era W Boyd, S Harper, PK Romano Argonne National Lab.(ANL), Argonne, IL (United States), 2016 | 3 | 2016 |
| Tally precision triggers for the OpenMC Monte Carlo code Q Shen, W Boyd, B Forget, K Smith Trans. Am. Nucl. Soc. 112, 637-640, 2015 | 3 | 2015 |
| Opencg: A Combinatorial Geometry Modeling Tool for Data Processing and Code Verification W Boyd, B Forget, K Smith American Nuclear Society (ANS), 2015 | 1 | 2015 |
| Interactive Visualization of Multi-Group Cross Sections on High-Fidelity Spatial Meshes L Abel, W Boyd, B Forget, K Smith Transactions of the American Nuclear Society 114 (1), 2016 | | 2016 |
| PINSPEC. A Monte Carlo code for pin cell spectral calculations for educational applications W Boyd, N Gibson, S Shaner, L Li, J Hunter, K Smith, B Forget | | 2015 |
