| Transport Theory JJ Duderstadt, WR Martin Wiley-Interscience, New York, 1979 | 1538 | 1979 |
| 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 |
| Diffusion synthetic acceleration of discontinuous finite element transport iterations ML Adams, WR Martin Nuclear science and engineering 111 (2), 145-167, 1992 | 131 | 1992 |
| Monte Carlo methods for radiation transport analysis on vector computers FB Brown, WR Martin Progress in Nuclear Energy 14 (3), 269-299, 1984 | 129 | 1984 |
| Assessing risk factors for transmission of infection JS Koopman, IM Longini Jr, JA Jacquez, CP Simon, DG Ostrow, ... American Journal of Epidemiology 133 (12), 1199-1209, 1991 | 126 | 1991 |
| Stochastic geometry capability in MCNP5 for the analysis of particle fuel FB Brown, WR Martin Annals of Nuclear Energy 31 (17), 2039-2047, 2004 | 106 | 2004 |
| On-the-fly Doppler broadening for Monte Carlo codes G Yesilyurt, WR Martin, FB Brown Nuclear science and engineering 171 (3), 239-257, 2012 | 97 | 2012 |
| Challenges and prospects for whole-core Monte Carlo analysis WR Martin Nuclear Engineering and Technology 44 (2), 151-160, 2012 | 84 | 2012 |
| SCALE continuous-energy eigenvalue sensitivity coefficient calculations CM Perfetti, BT Rearden, WR Martin Nuclear Science and Engineering 182 (3), 332-353, 2016 | 77 | 2016 |
| Development of safety analysis codes and experimental validation for a very high temperature gas-cooled reactor Final report C Oh Idaho National Lab.(INL), Idaho Falls, ID (United States), 2006 | 76 | 2006 |
| Theory and applications of the fission matrix method for continuous-energy Monte Carlo S Carney, F Brown, B Kiedrowski, W Martin Annals of Nuclear Energy 73, 423-431, 2014 | 75 | 2014 |
| Finite element solutions of the neutron transport equation with applications to strong heterogeneities WR Martin, JJ Duderstadt Nuclear Science and Engineering 62 (3), 371-390, 1977 | 75 | 1977 |
| The Monte Carlo performance benchmark test-aims, specifications and first results JE Hoogenboom, WR Martin, B Petrovic International Conference on Mathematics and Computational Methods Applied to …, 2011 | 67 | 2011 |
| Monte Carlo-advances and challenges FB Brown, WR Martin, RD Mosteller Workshop at PHYSOR-2008, Interlaken, Switzerland, 14-19, 2008 | 64 | 2008 |
| Pseudo material construct for coupled neutronic-thermal-hydraulic analysis of VHTGR JL Conlin, W Ji, JC Lee, WR Martin Trans. Am. Nucl. Soc 92, 225-227, 2005 | 57 | 2005 |
| Monte Carlo performance benchmark for detailed power density calculation in a full size reactor core JE Hoogenboom, WR Martin, B Petrovic Benchmark specifications revision 1 (1), 2011 | 56 | 2011 |
| Fission matrix capability for MCNP, part I-Theory FB Brown, SE Carney, BC Kiedrowski, WR Martin Mathematics & Computation, 2013 | 54 | 2013 |
| Phase-space finite element methods applied to the first-order form of the transport equation WR Martin, CE Yehnert, L Lorence, JJ Duderstadt Annals of Nuclear Energy 8 (11-12), 633-646, 1981 | 54 | 1981 |
| A full-core resonance self-shielding method using a continuous-energy quasi–one-dimensional slowing-down solution that accounts for temperature-dependent fuel subregions and … Y Liu, W Martin, M Williams, KS Kim Nuclear Science and Engineering 180 (3), 247-272, 2015 | 52 | 2015 |
| Status of vectorized Monte Carlo for particle transport analysis WR Martin, FB Brown The International Journal of Supercomputing Applications 1 (2), 11-32, 1987 | 51 | 1987 |
