| Design and experimental study of ORC (organic Rankine cycle) and radial turbine using R245fa working fluid SH Kang Energy 41 (1), 514-524, 2012 | 574 | 2012 |
| Design and preliminary tests of ORC (organic Rankine cycle) with two-stage radial turbine SH Kang Energy 96, 142-154, 2016 | 92 | 2016 |
| A preliminary safety analysis for the prototype gen IV sodium-cooled fast reactor KL Lee, KS Ha, JH Jeong, CW Choi, T Jeong, SJ Ahn, SW Lee, ... Nuclear Engineering and Technology 48 (5), 1071-1082, 2016 | 30 | 2016 |
| Finite element formulation of the first-and second-order discrete ordinates equations for radiative heat transfer calculation in three-dimensional participating media SH Kang, TH Song Journal of Quantitative Spectroscopy and Radiative Transfer 109 (11), 2094-2107, 2008 | 27 | 2008 |
| Evaluation of a sodium–water reaction event caused by steam generator tubes break in the prototype generation IV sodium-cooled fast reactor SJ Ahn, KS Ha, WP Chang, SH Kang, KL Lee, CW Choi, SW Lee, J Yoo, ... Nuclear Engineering and Technology 48 (4), 952-964, 2016 | 25 | 2016 |
| Design and experimental study of organic Rankine cycle (ORC) and radial turbine SH Kang, DH Chung Turbo Expo: Power for Land, Sea, and Air 54631, 1037-1043, 2011 | 11 | 2011 |
| Advances in the development of the SAS4A code metallic fuel models for the analysis of prototype Gen-IV sodium-cooled fast reactor postulated severe accidents A Tentner, A Karahan, S Kang | 9 | 2017 |
| Conservative interpretation of nonconservative discrete ordinates radiative intensity distribution K Kim, SH Kang, TH Song Heat Transfer Summer Conference 43567, 67-75, 2009 | 8 | 2009 |
| Overview of the SAS4A metallic fuel models and extended analysis of a postulated severe accident in the prototype gen-IV sodium-cooled fast reactor AM Tentner, A Karahan, SH Kang Nuclear Technology 206 (2), 242-254, 2020 | 7 | 2020 |
| Numerical analysis to design high temperature heat exchanger of beta type stirling engine in 3-D combustion field SH Kang, HJ Kim, DH Chung Journal of computational fluids engineering 16 (2), 56-61, 2011 | 7 | 2011 |
| Advances in the development of the SAS4A code metallic fuel models for the analysis of PGSFR postulated severe accidents A Tentner, A Karahan, S Kang | 5 | 2017 |
| 'Corrigendum to" Design and experimental study of ORC (organic Rankine cycle) and radial turbine using R245fa working fluid"[Energy 41 (2012) 514-524]' SH Kang Energy 43 (1), 490-490, 2012 | 4 | 2012 |
| Validation of the correlation-based aerosol model in the ISFRA sodium-cooled fast reactor safety analysis code C Yoon, SI Kim, SJ Lee, SH Kang, CY Paik Nuclear Engineering and Technology 53 (12), 3966-3978, 2021 | 3 | 2021 |
| Recent Activities of the Safety and Operation Project of the Sodium-Cooled Fast Reactor in the Generation IV International Forum A Vasile, L Ren, T Fanning, H Tsige-Tamirat, H Yamano, SH Kang, ... | 3 | 2017 |
| Numerical Analysis on the Reactor Core Expansion and Energy Behaviors During CDA Using Underwater Explosion Theory SH Kang Journal of computational fluids engineering 21 (3), 8-14, 2016 | 3 | 2016 |
| Investigation of axial blockage position effect in the SFR flow blockage analysis WP Chang, KL Lee, SH Kang, CW Choi, HY Jeong Proceedings of Korean Nuclear Society Autumn Meeting, Gyeongju, Korea, 2012 | 3 | 2012 |
| Activities of the GIF Safety and Operation project of sodium-cooled fast reactor systems H Yamano, A Vasile, SH Kang, T Summer, H Tsige-Tamirat, J Wang, ... The Proceedings of the International Conference on Nuclear Engineering …, 2019 | 2 | 2019 |
| Validation of advanced in-pin metallic fuel models of SAS4A A Karahan, AM Tentner, SH Kang Transactions of the American Nuclear Society 115, 2016 | 2 | 2016 |
| Safety Analyses of Design Basis and Design Extended Condition Events for the PGSFR SH Kang, KL Lee, CW Choi, JH Jeong, TK Jeong, KS Ha Transactions of the American Nuclear Society 114 (1), 2016 | 2 | 2016 |
| Evaluation on In-vessel Source Term in PGSFR (2015 Results) SW Lee, WP Chang, KS Ha, SJ Ahn, SH Kang, CW Choi, KL Lee, ... Transactions of the Korean Nuclear Society Spring Meeting Jeju, Korea, 2016 | 2 | 2016 |
