| Direct-contact condensation of pure steam on co-current and counter-current stratified liquid flow in a circular pipe HS Park, SW Choi, HC No International Journal of Heat and Mass Transfer 52 (5-6), 1112-1122, 2009 | 24 | 2009 |
| Assessment of passive safety system performance under main steam line break accident J Lim, SW Choi, J Yang, DY Lee, S Rassame, T Hibiki, M Ishii Annals of Nuclear Energy 64, 287-294, 2014 | 19 | 2014 |
| Assessment of performance of BWR passive safety systems in a small break LOCA with integral testing and code simulation J Yang, SW Choi, J Lim, DY Lee, S Rassame, T Hibiki, M Ishii Nuclear engineering and design 247, 128-135, 2012 | 19 | 2012 |
| Assessment of passive safety system performance under gravity driven cooling system drain line break accident J Lim, J Yang, SW Choi, DY Lee, S Rassame, T Hibiki, M Ishii Progress in Nuclear Energy 74, 136-142, 2014 | 18 | 2014 |
| Counterpart experimental study of ISP-42 PANDA tests on PUMA facility J Yang, SW Choi, J Lim, DY Lee, S Rassame, T Hibiki, M Ishii Nuclear Engineering and Design 258, 249-257, 2013 | 15 | 2013 |
| Interfacial structure in an air–water planar bubble jet X Sun, S Vasavada, SW Choi, S Kim, M Ishii, SG Beus Experiments in fluids 38, 426-439, 2005 | 12 | 2005 |
| Experimental investigation of void distribution in Suppression Pool during the initial blowdown period of a Loss of Coolant Accident using air–water two-phase mixture S Rassame, M Griffiths, J Yang, DY Lee, P Ju, SW Choi, T Hibiki, M Ishii Annals of Nuclear Energy 73, 53-67, 2014 | 11 | 2014 |
| Behaviors of passive safety systems under a Feed Water Line Break LOCA on a Generation III+ Boiling Water Reactor J Yang, J Lim, SW Choi, DY Lee, S Rassame, T Hibiki, M Ishii Progress in Nuclear Energy 83, 35-42, 2015 | 7 | 2015 |
| Scaling and Scientific Design Study for GE ESBWR Relative to PUMA Facility with Volume Ratio of 1/580 M Ishii, K Vierow, K Iyer, L Cheng, SW Choi, KS Woo, J Lim, T Norman, ... Purdue University Report PU/NE-06-01, 2006 | 6 | 2006 |
| Scaling and scientific design study for GE ESBWR relative to PUMA Facility with volume ratio of 1/580, Purdue University Report PU M Ishii, K Vierow, K Iyer, L Cheng, SW Choi, KS Woo, J Lim, T Norman, ... NE-06-01, 2006 | 6 | 2006 |
| Scaling, experiment, and code assessment on an integral testing facility J Yang, SW Choi, J Lim, DY Lee, S Rassame, T Hibiki, M Ishii | 3 | 2011 |
| A Data Report on PUMA-E Small Break LOCA GDCS Drain Line Break Test with One ICS Unit Disabled M Ishii, T Hibiki, J Lim, DY Lee, S Rassame, SW Choi, J Yang Purdue University Report, PU/NE-08-23, 2008 | 3 | 2008 |
| PCCS Separate Effect Tests in the PUMA Facility M Ishii, SW Choi, J Yang, K Vierow, W Wang, J Han PU/NE-05-17, Purdue University, 2006 | 3 | 2006 |
| PUMA-PCCS separate effect tests and RELAP5 code evaluation in PUMA SW Choi Ph. D. Thesis, 2009 | 2 | 2009 |
| Behavior of containment emergency systems M Ishii, YJ Yoo, L Cheng, SW Choi, J Yang, N Aksan, M Kondo, ... Purdue University, West Lafayette, IN, 2007 | 2 | 2007 |
| Performance analysis of passively safe BWR with experimental and numerical simulation J Yang, SW Choi, J Lim, DY Lee, S Rassame, T Hibiki, M Ishii 19th International Conference on Nuclear Engineering, 2011 | 1 | 2011 |
| Improvement of auditing technology of safety analysis through thermal-hydraulic separate effect tests HC No, YM Moon, DW Lee, SI Lee, ES Kim, KS Yeom Korea Institute of Nuclear Safety, 2002 | 1 | 2002 |
| Direct-contact condensation experiments for the stratified liquid flow with steam and steam/air mixture in a circular pipe SW Choi, HS PARK, NO Hee Cheon | 1 | 2000 |
| ICONE19-43961 Performance Analysis of Passively Safe BWR with Experimental and Numerical Simulation J Yang, SW Choi, J Lim, DY Lee, S Rassame, T Hibiki, M Ishii The Proceedings of the International Conference on Nuclear Engineering …, 2011 | | 2011 |
| TRACE Assessment for Application to Anticipated Operational Occurrences in Boiling Water Reactors S Vasavada, S Choi, M Zavisca, M Khatib-Rahbar, J Staudenmeier, ... Transactions of the American Nuclear Society 104, 1006, 2011 | | 2011 |
