| 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 |
| PARCS: Purdue advanced reactor core simulator TJ Downar, DA Barber, RM Miller, CH Lee, T Kozlowski, D Lee, Y Xu, ... 2002 International Conference on the New Frontiers of Nuclear Technology …, 2002 | 161 | 2002 |
| PARCS v2. 7 US NRC Core Neutronics Simulator User Manual T Downar, Y Xu, T Kozlowski, D Carlson School of Nuclear Engineering Purdue University, 2006 | 158 | 2006 |
| 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 |
| PARCS v2. 6 US NRC Core Neutronics Simulator T Downar, D Lee, Y Xu, T Kozlowski, J Staudenmier Theory manual, 2004 | 96 | 2004 |
| Resonance treatment using pin-based pointwise energy slowing-down method S Choi, C Lee, D Lee Journal of computational physics 330, 134-155, 2017 | 94 | 2017 |
| Verification and validation of STREAM/RAST-K for PWR analysis J Choe, S Choi, P Zhang, J Park, W Kim, HC Shin, HS Lee, JE Jung, ... Nuclear Engineering and Technology 51 (2), 356-368, 2019 | 81 | 2019 |
| MCS–A Monte Carlo particle transport code for large-scale power reactor analysis H Lee, W Kim, P Zhang, M Lemaire, A Khassenov, J Yu, Y Jo, J Park, ... Annals of Nuclear Energy 139, 107276, 2020 | 79 | 2020 |
| 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 |
| Impact of inflow transport approximation on light water reactor analysis S Choi, K Smith, HC Lee, D Lee Journal of Computational Physics 299, 352-373, 2015 | 60 | 2015 |
| Validation of UNIST Monte Carlo code MCS for criticality safety analysis of PWR spent fuel pool and storage cask J Jang, W Kim, S Jeong, E Jeong, J Park, M Lemaire, H Lee, Y Jo, ... Annals of Nuclear Energy 114, 495-509, 2018 | 59 | 2018 |
| Resonance self-shielding methodology of new neutron transport code STREAM S Choi, H Lee, SG Hong, D Lee Journal of Nuclear Science and Technology 52 (9), 1133-1150, 2015 | 48 | 2015 |
| Cell homogenization method for pin-by-pin neutron transport calculations T Kozlowski, Y Xu, TJ Downar, D Lee Nuclear science and engineering 169 (1), 1-18, 2011 | 46 | 2011 |
| New burnable absorber for long-cycle low boron operation of PWRs J Choe, HC Shin, D Lee Annals of Nuclear Energy 88, 272-279, 2016 | 42 | 2016 |
| On the diffusion coefficient calculation in two-step light water reactor core analysis S Choi, KS Smith, H Kim, T Tak, D Lee Journal of Nuclear Science and Technology 54 (6), 705-715, 2017 | 41 | 2017 |
| Investigation of CMFD accelerated Monte Carlo eigenvalue calculation with simplified low dimensional multigroup formulation MJ Lee, HG Joo, D Lee, K Smith Proc. PHYSOR 2010, 9-14, 2010 | 40 | 2010 |
| Three-dimensional method of characteristics/diamond-difference transport analysis method in STREAM for whole-core neutron transport calculation S Choi, D Lee Computer Physics Communications 260, 107332, 2021 | 38 | 2021 |
| MCS based neutronics/thermal-hydraulics/fuel-performance coupling with CTF and FRAPCON J Yu, H Lee, M Lemaire, H Kim, P Zhang, D Lee Computer Physics Communications 238, 1-18, 2019 | 38 | 2019 |
| Convergence analysis of the nonlinear coarse-mesh finite difference method for one-dimensional fixed-source neutron diffusion problem D Lee, TJ Downar, Y Kim Nuclear science and engineering 147 (2), 127-147, 2004 | 38 | 2004 |
| A new approach to three-dimensional neutron transport solution based on the method of characteristics and linear axial approximation Y Zheng, S Choi, D Lee Journal of Computational Physics 350, 25-44, 2017 | 37 | 2017 |
