| Assessment of RELAP5/MOD3. 2.2 γ against flooding database in horizontal-to-inclined pipes HT Kim, HC No Annals of Nuclear Energy 29 (7), 835-850, 2002 | 42 | 2002 |
| Assessment of RELAP5/MOD3. 2.2 γ against flooding database in horizontal-to-inclined pipes HT Kim, HC No Annals of Nuclear Energy 29 (7), 835-850, 2002 | 42 | 2002 |
| Moderator analysis of Wolsong units 2/3/4 for the 35% reactor inlet header break with a loss of emergency core cooling injection C Yoon, BW Rhee, HT Kim, JH Park, BJ Min Journal of Nuclear Science and Technology 43 (5), 505-513, 2006 | 40 | 2006 |
| Performance evaluation of UO2/graphene composite fuel and SiC cladding during LBLOCA using MARS-KS SW Lee, HT Kim, IC Bang Nuclear engineering and design 257, 139-145, 2013 | 26 | 2013 |
| Benchmark calculations of a radiation heat transfer for a CANDU fuel channel analysis using the CFD code HT Kim, BW Rhee, JH Park Journal of Nuclear Science and Technology 43 (11), 1422-1430, 2006 | 25 | 2006 |
| An experimental study on natural convection heat transfer of liquid gallium in a rectangular loop S Kang, KS Ha, HT Kim, JH Kim, IC Bang International Journal of Heat and Mass Transfer 66, 192-199, 2013 | 22 | 2013 |
| Numerical study for CANDU moderator temperature prediction by using the two-phase flow analysis code, CUPID JR Lee, SG Park, HY Yoon, HT Kim, JJ Jeong Annals of Nuclear Energy 59, 139-148, 2013 | 14 | 2013 |
| Computational fluid dynamics analysis of the Canadian deuterium uranium moderator tests at the Stern Laboratories Inc. HT Kim, SM Chang Nuclear Engineering and Technology 47 (3), 284-292, 2015 | 12 | 2015 |
| CFX simulation of a horizontal heater rods test HT Kim, BW Rhee, JH Park Nuclear engineering and design 238 (3), 522-529, 2008 | 12 | 2008 |
| Performance of internally and externally cooled annular fuel in a loss of coolant accident HT Kim, P Hejzlar, MS Kazimi, HC No American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL …, 2002 | 12 | 2002 |
| PIV measurements of the flow patterns in a CANDU-6 model S Im, HT Kim, BW Rhee, HJ Sung Annals of Nuclear Energy 98, 1-11, 2016 | 11 | 2016 |
| Scaled-down moderator circulation test facility at Korea Atomic Energy Research Institute HT Kim, BW Rhee Science and Technology of Nuclear Installations 2016, 2016 | 11 | 2016 |
| Measurement of velocity and temperature profiles in the scaled-down CANDU-6 moderator tank HT Kim, JE Cha, BW Rhee, HL Choi, H Seo, IC Bang International Conference on Nuclear Engineering 55812, V004T09A050, 2013 | 11 | 2013 |
| Status of moderator circulation test at Korea atomic energy research institute HT Kim, BW Rhee, JE Cha, HL Choi Proceedings of the Korea Nuclear Society Spring Meeting, 2013 | 11 | 2013 |
| Application of a Zircaloy/Steam oxidation model to a CFD code and its validation against a CANDU fuel channel experiment: CS28-2 HT Kim, BW Rhee, JH Park Journal of nuclear science and technology 44 (11), 1385-1394, 2007 | 11 | 2007 |
| Preliminary CFD analysis of the moderator circulation test HT Kim, JE Cha, BW Rhee, HL Choi 1 st International Workshop on Advanced CANDU Technology, Daejeon, Korea, 2012 | 9 | 2012 |
| CFX simulation of high temperature thermal–chemical experiment: CS28-2 HT Kim, BW Rhee, JH Park Annals of Nuclear Energy 35 (4), 677-689, 2008 | 9 | 2008 |
| Assessment of the CUPID code applicability to the thermal-hydraulic analysis of a CANDU moderator system SK Park, JJ Jeong, JR Lee, HY Yoon, HT Kim Progress in Nuclear Energy 75, 72-79, 2014 | 8 | 2014 |
| The feasibility of multidimensional CFD applied to calandria system in the moderator of CANDU-6 PHWR using commercial and open-source codes HT Kim, SM Chang, JH Shin, YG Kim Science and Technology of Nuclear Installations 2016, 2016 | 7 | 2016 |
| A Scaling Analysis of a CANDU-6 moderator tank scaled-down test facility BW Rhee, HT Kim, SK Park, JE Cha, HL Choi International Conference on Nuclear Engineering 55812, V004T09A021, 2013 | 7 | 2013 |
