| Methods and performance of a three-dimensional whole-core transport code DeCART HG Joo, JY Cho, KS Kim, CC Lee, SQ Zee American Nuclear Society, 2004 | 297 | 2004 |
| Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers YS Jung, CB Shim, CH Lim, HG Joo Annals of Nuclear Energy 62, 357-374, 2013 | 265 | 2013 |
| PARCS: a multi-dimensional two-group reactor kinetics code based on the nonlinear analytic nodal method HG Joo, D Barber, G Jiang, TJ Downar PARCS Manual Version 2, 1998 | 166 | 1998 |
| 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 | 164 | 2002 |
| Master-3.0: multi-purpose analyzer for static and transient effects of reactors BO Cho, HG Joo, JY Cho, JS Song, SQ Zee Korea Atomic Energy Research Institute, 2002 | 100 | 2002 |
| Solution of the BEAVRS benchmark using the nTRACER direct whole core calculation code M Ryu, YS Jung, HH Cho, HG Joo Journal of Nuclear Science and Technology 52 (7-8), 961-969, 2015 | 96 | 2015 |
| Dynamic implementation of the equivalence theory in the heterogeneous whole core transport calculation HG Joo, JY Cho American Nuclear Society, 2002 | 91 | 2002 |
| Two-level coarse mesh finite difference formulation with multigroup source expansion nodal kernels JI Yoon, HG Joo Journal of Nuclear Science and Technology 45 (7), 668-682, 2008 | 82 | 2008 |
| Axial SPN and Radial MOC Coupled Whole Core Transport Calculation JY Cho, KS Kim, CC Lee, SQ Zee, HG Joo Journal of nuclear science and technology 44 (9), 1156-1171, 2007 | 81 | 2007 |
| PASCAR: Long burning small modular reactor based on natural circulation S Choi, JH Cho, MH Bae, J Lim, D Puspitarini, JH Jeun, HG Joo, ... Nuclear Engineering and Design 241 (5), 1486-1499, 2011 | 73 | 2011 |
| Cell based CMFD formulation for acceleration of whole-core method of characteristics calculations JY Cho, HG Joo, KS Kim, SQ Zee Nuclear Engineering and Technology 34 (3), 250-258, 2002 | 73 | 2002 |
| 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 | 70 | 2014 |
| High-fidelity light water reactor analysis with the numerical nuclear reactor DP Weber, T Sofu, WS Yang, TJ Downar, JW Thomas, Z Zhong, JY Cho, ... Nuclear Science and Engineering 155 (3), 395-408, 2007 | 70 | 2007 |
| Whole core transport calculation employing hexagonal modular ray tracing and CMFD formulation JY Cho, KS Kim, HJ Shim, JS Song, CC Lee, HG Joo Journal of nuclear science and technology 45 (8), 740-751, 2008 | 69 | 2008 |
| Generation of few-group diffusion theory constants by Monte Carlo code McCARD HJ Park, HJ Shim, HG Joo, CH Kim Nuclear science and engineering 172 (1), 66-77, 2012 | 67 | 2012 |
| Subgroup weight generation based on shielded pin-cell cross section conservation HG Joo, GY Kim, L Pogosbekyan Annals of Nuclear Energy 36 (7), 859-868, 2009 | 67 | 2009 |
| Solution of the C5G7MOX benchmark three-dimensional extension problems by the DeCART direct whole core calculation code JY Cho, HG Joo Progress in Nuclear Energy 48 (5), 456-466, 2006 | 55 | 2006 |
| Multigroup pin power reconstruction with two-dimensional source expansion and corner flux discontinuity HG Joo, JI Yoon, SG Baek Annals of Nuclear Energy 36 (1), 85-97, 2009 | 51 | 2009 |
| Multiobjective loading pattern optimization by simulated annealing employing discontinuous penalty function and screening technique TK Park, HG Joo, CH Kim, HC Lee Nuclear Science and Engineering 162 (2), 134-147, 2009 | 45 | 2009 |
| An incomplete domain decomposition preconditioning method for nonlinear nodal kinetics calculations HG Joo, TJ Downar Nuclear science and engineering 123 (3), 403-414, 1996 | 45 | 1996 |
