| 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 | 759 | 2015 |
| Assembly homogenization techniques for light water reactor analysis KS Smith Progress in Nuclear Energy 17 (3), 303-335, 1986 | 588 | 1986 |
| Nodal method storage reduction by nonlinear iteration KS Smith Transactions of the American Nuclear Society 44, 1983 | 362 | 1983 |
| An analytic nodal method for solving the two-group, multidimensional, static and transient neutron diffusion equations KS Smith Massachusetts Institute of Technology, 1979 | 341 | 1979 |
| Benchmark for evaluation and validation of reactor simulations (BEAVRS), v1. 0.1 N Horelik, B Herman, B Forget, K Smith Proc. Int. Conf. Mathematics and Computational Methods Applied to Nuc. Sci …, 2013 | 300 | 2013 |
| CASMO-5 development and applications J Rhodes, K Smith, D Lee Proceedings of the PHYSOR-2006 conference, ANS Topical Meeting on Reactor …, 2006 | 246 | 2006 |
| Full-core, 2-D, LWR core calculation with CASMO-4E KS Smith Proc. Int. Conf. on the New Frontiers of Nuclear Technology: Reactor Physics …, 2002 | 219 | 2002 |
| 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 |
| Spatial homogenization methods for light water reactor analysis KS Smith Massachusetts Institute of Technology, 1980 | 180 | 1980 |
| SIMULATE-3 pin power reconstruction: methodology and benchmarking KR Rempe, KS Smith, AF Henry Nuclear Science and Engineering 103 (4), 334-342, 1989 | 145 | 1989 |
| The impact of 238U resonance elastic scattering approximations on thermal reactor Doppler reactivity D Lee, K Smith, J Rhodes Annals of Nuclear Energy 36 (3), 274-280, 2009 | 131 | 2009 |
| Optimization of pressurized water reactor shuffling by simulated annealing with heuristics JG Stevens, KS Smith, KR Rempe, TJ Downar Nuclear Science and Engineering 121 (1), 67-88, 1995 | 131 | 1995 |
| CASMO-4 characteristics method for two-dimensional PWR and BWR core calculations KS Smith Trans. Am. Nucl. Soc. 83, 294, 2000 | 102 | 2000 |
| Direct Doppler broadening in Monte Carlo simulations using the multipole representation B Forget, S Xu, K Smith Annals of Nuclear Energy 64, 78-85, 2014 | 85 | 2014 |
| Coarse mesh finite difference formulation for accelerated Monte Carlo eigenvalue calculation MJ Lee, HG Joo, D Lee, K Smith Annals of Nuclear Energy 65, 101-113, 2014 | 68 | 2014 |
| Application of the Jacobian-free Newton-Krylov method to nonlinear acceleration of transport source iteration in slab geometry DA Knoll, H Park, K Smith Nuclear Science and Engineering 167 (2), 122-132, 2011 | 68 | 2011 |
| QPANDA: an advanced nodal method for LWR analyses KS Smith, DM Ver Planck, M Edenius Trans. Am. Nucl. Soc.;(United States) 50 (CONF-851115-), 1985 | 68 | 1985 |
| SIMULATE-3. Advanced three-dimensional two-group reactor analysis code JT Cronin, KS Smith, DM Ver Planck Studsvik/SOA-95/18, 1995 | 67 | 1995 |
| Practical and efficient iterative method for LWR fuel assembly homogenization KS Smith Transactions of the American Nuclear Society 71 (CONF-941102-), 1994 | 66 | 1994 |
| Windowed multipole for cross section Doppler broadening C Josey, P Ducru, B Forget, K Smith Journal of Computational Physics 307, 715-727, 2016 | 62 | 2016 |
