| Two-phase natural circulation flow of air and water in a reactor cavity model under an external vessel cooling during a severe accident RJ Park, KS Ha, SB Kim, HD Kim Nuclear engineering and design 236 (23), 2424-2430, 2006 | 43 | 2006 |
| OECD/NEA/CSNI status report on filtered containment venting D Jacquemain, S Guentay, S Basu, M Sonnenkalb, L Lebel, J Ball, ... Organisation for Economic Co-Operation and Development, 2014 | 39 | 2014 |
| A core catcher design for advanced light water reactors JH Song, HY Kim, KS Ha, RJ Park, JT Kim | 39 | 2011 |
| Evaluation of heat-flux distribution at the inner and outer reactor vessel walls under the in-vessel retention through external reactor vessel cooling condition J Jung, SM An, KS Ha, HY Kim Nuclear Engineering and Technology 47 (1), 66-73, 2015 | 34 | 2015 |
| Validation of RCS depressurization strategy and core coolability map for independent scenarios of SBLOCA, SBO, and TLOFW S Lee, KS Ha, HY Kim, SJ Kim Journal of Nuclear Science and Technology 51 (2), 181-195, 2014 | 26 | 2014 |
| CUPID code manual volume I: Mathematical models and solution methods HY Yoon, KD Kim, JW Kim, JT Kim, IK Park, JR Lee, SJ Lee, BD Chung, ... Korea Atomic Energy Research Institute, 2011 | 25 | 2011 |
| Detailed evaluation of natural circulation mass flow rate in the annular gap between the outer reactor vessel wall and insulation under IVR-ERVC RJ Park, KS Ha, HY Kim Annals of Nuclear Energy 89, 50-55, 2016 | 24 | 2016 |
| A study of the two-phase natural circulation flow through the annular gap between a reactor vessel and insulation system KS Ha, RJ Park, HY Kim, SB Kim, HD Kim International communications in heat and mass transfer 31 (1), 43-52, 2004 | 24 | 2004 |
| Thermal hydraulic issues of containment filtered venting system for a long operating time YS Na, KS Ha, RJ Park, JH Park, SW Cho Nuclear Engineering and Technology 46 (6), 797-802, 2014 | 23 | 2014 |
| An experimental study on layer inversion in the corium pool during a severe accident KH Kang, RJ Park, SH Hong, SW Hong, KS Ha Nuclear Engineering and Design 278, 163-170, 2014 | 20 | 2014 |
| Numerical investigation of the spreading and heat transfer characteristics of ex-vessel core melt IS Ye, JA Kim, C Ryu, KS Ha, HY Kim, J Song Nuclear Engineering and Technology 45 (1), 21-28, 2013 | 19 | 2013 |
| A comparative study of the MATRA-LMR-FB calculation with the SABRE result for the flow blockage accident in the sodium cooled fast reactor WP Chang, KS Ha, SD Suk, HY Jeong Nuclear engineering and design 241 (12), 5225-5237, 2011 | 19 | 2011 |
| Experimental study on critical power in a hemispherical narrow gap RJ Park, KS Ha, SB Kim, HD Kim, JH Jeong Nuclear technology 140 (3), 266-278, 2002 | 19 | 2002 |
| SIRIUS: a code on fission product behavior under severe accident KS Ha, SI Kim, HS Kang, DH Kim Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, 2017 | 17 | 2017 |
| Analysis of Fukushima unit 2 accident considering the operating conditions of RCIC system SI Kim, JH Park, KS Ha, SW Cho, JH Song Nuclear Engineering and Design 298, 183-191, 2016 | 16 | 2016 |
| Prediction of boiling-induced natural-circulation flow in engineered cooling channels KS Ha, FB Cheung, J Song, RJ Park, SB Kim Nuclear Technology 181 (1), 196-207, 2013 | 16 | 2013 |
| Loop analysis of a natural circulation two-phase flow under an external reactor vessel cooling JC Kim, KS Ha, RJ Park, SB Kim, SW Hong International communications in heat and mass transfer 35 (8), 1001-1006, 2008 | 16 | 2008 |
| Detailed evaluation of two phase natural circulation flow in the cooling channel of the ex-vessel core catcher for EU-APR1400 RJ Park, KS Ha, BW Rhee, HY Kim Nuclear Engineering and Design 298, 33-40, 2016 | 15 | 2016 |
| Ablation characteristics of special concrete due to an impinging zirconium-dioxide melt jet SM An, KS Ha, BT Min, HY Kim, JH Song Nuclear Engineering and Design 284, 10-18, 2015 | 15 | 2015 |
| Evaluation of in-vessel corium retention through external reactor vessel cooling for small integral reactor RJ Park, JR Lee, KS Ha, HY Kim Nuclear Engineering and Design 262, 571-578, 2013 | 15 | 2013 |
