| 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 | 262 | 2013 |
| 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 | 95 | 2015 |
| 2.0-MOOSE: Enabling massively parallel multiphysics simulation AD Lindsay, DR Gaston, CJ Permann, JM Miller, D Andrš, AE Slaughter, ... SoftwareX 20, 101202, 2022 | 94 | 2022 |
| Griffin software development plan C Lee, YS Jung, H Park, ER Shemon, J Ortensi, Y Wang, VM Labouré, ... Idaho National Lab.(INL), Idaho Falls, ID (United States); Argonne National …, 2021 | 59* | 2021 |
| Application of backward differentiation formula to spatial reactor kinetics calculation with adaptive time step control CB Shim, YS Jung, JI Yoon, HG Joo Nuclear Engineering and Technology 43 (6), 531-546, 2011 | 31 | 2011 |
| PROTEUS-MOC user manual YS Jung, C Lee, MA Smith Argonne National Lab.(ANL), Argonne, IL (United States), 2018 | 28 | 2018 |
| Consistent pCMFD acceleration schemes of the three-dimensional transport code PROTEUS-MOC G Zhang, A Hsieh, WS Yang, YS Jung Nuclear Science and Engineering, 2019 | 25 | 2019 |
| Incorporation of anisotropic scattering in nTRACER M Ryu, YS Jung, CH Lim, HG Joo Transactions of the Korean Nuclear Society Autumn Meeting, Pyeongchang, Korea, 2014 | 25 | 2014 |
| A Consistent CMFD Formulation for the Acceleration of Neutron Transport Calculations Based on the Finite Element Method YS Jung, WS Yang Nuclear Science and Engineering 185 (2), 307-324, 2017 | 24 | 2017 |
| Decoupled planar MOC solution for dynamic group constant generation in direct three-dimensional core calculations YS Jung, HG Joo Proc. M&C, 3-7, 2009 | 24 | 2009 |
| PROTEUS-NODAL user manual YS Jung, C Lee, MA Smith Argonne National Lab.(ANL), Argonne, IL (United States), 2018 | 19 | 2018 |
| Temperature dependent subgroup formulation with number density adjustment for direct whole core power reactor calculation YS Jung, CH Lim, HG Joo Annals of Nuclear Energy 96, 249-263, 2016 | 16 | 2016 |
| Micro reactor simulation using the PROTEUS suite in FY19 C Lee, YS Jung, HK Cho Argonne National Lab.(ANL), Argonne, IL (United States), 2019 | 15 | 2019 |
| Implementation of the transient fixed-source problem in the neutron transport code PROTEUS-MOC TN Nguyen, YS Jung, T Downar, C Lee Annals of Nuclear Energy 129, 199-206, 2019 | 15 | 2019 |
| Status of the NEAMS and ARC neutronic fast reactor tools integration to the NEAMS Workbench N Stauff, P Lartaud, YS Jung, CH Lee, K Zeng, J Hou Argonne National Lab.(ANL), Argonne, IL (United States), 2019 | 14 | 2019 |
| Control Rod Decusping Treatment Based on Local 3-D CMFD Calculation for Direct Whole Core Transport Solvers YS Jung, HG Joo Proceedings of the International Congress on Advances in Nuclear Power …, 2014 | 14 | 2014 |
| Generation of the Cross Section Library for PROTEUS C Lee, YS Jung Argonne National Lab.(ANL), Argonne, IL (United States), 2018 | 13 | 2018 |
| Extension of MC2-3 for generation of multigroup cross sections in thermal energy range BK Jeon, WS Yang, YS Jung, CH Lee Proceedings of M&C 2017 Conference, Jeju, Korea, 2017 | 12 | 2017 |
| Simulation of TREAT Cores Using High-Fidelity Neutronics Code PROTEUS CH Lee, YS Jung, HM Connaway, TA Taiwo Proc. of M&C 2017, 16-20, 2017 | 11 | 2017 |
| Solution of the BEAVRS benchmark using the nTRACER direct whole core transport code M Ryu, YS Jung, HH Cho, H Joo Proc. PHYSOR 2014, 2014 | 11 | 2014 |
