| Flow-induced vibration and fretting-wear predictions of steam generator helical tubes JC Jo, MJ Jhung Nuclear engineering and design 238 (4), 890-903, 2008 | 50 | 2008 |
| Equivalent material properties of perforated plate with triangular or square penetration pattern for dynamic analysis MJ Jhung, JC Jo Nuclear engineering and technology 38 (7), 689-696, 2006 | 37 | 2006 |
| Numerical analysis of unsteady conjugate heat transfer and thermal stress for a curved piping system subjected to thermal stratification JC Jo, YH Choi, SK Choi J. Pressure Vessel Technol. 125 (4), 467-474, 2003 | 33 | 2003 |
| Fluidelastic instability analysis of operating nuclear steam generator U-tubes JC Jo, WK Shin Nuclear engineering and design 193 (1-2), 55-71, 1999 | 33 | 1999 |
| CFD analysis of thermally stratified flow and conjugate heat transfer in a PWR pressurizer surgeline JC Jo, DG Kang | 31 | 2010 |
| Numerical simulation of subcooled flow boiling heat transfer in helical tubes JC Jo, WS Kim, CY Choi, YK Lee | 31 | 2009 |
| Numerical analysis of thermal stratification in a circular pipe JC Jo, YI Kim, SK Choi J. Pressure Vessel Technol. 123 (4), 517-524, 2001 | 29 | 2001 |
| Dynamic characteristics of steam generator U-tubes with defect JC Jo, MJ Jhung, WS Kim, HJ Kim Nuclear Engineering and design 235 (7), 821-831, 2005 | 22 | 2005 |
| Fluid-structure interactions JC Jo Korea institute of Nuclear safety, Republic of Korea, 2004 | 19 | 2004 |
| Multidimensional phase change problems by the dual-reciprocity boundary-element method JC Jo, WK Shin, CY Choi Numerical Heat Transfer: Part B: Fundamentals 36 (1), 95-113, 1999 | 19 | 1999 |
| Transient Thermal-Hydraulic Responses of the Nuclear Steam Generator Secondary Side to a Main Steam Line Break JC Jo, FJ Moody Journal of Pressure Vessel Technology 137 (4), 041301, 2015 | 18 | 2015 |
| 3D modeling of fluid-structure interaction with external flow using coupled LBM and FEM YW Kwon, JC Jo | 18* | 2008 |
| Impact analysis of a water storage tank MJ Jhung, JC Jo, SJ Jeong Nuclear Engineering and Technology 38 (7), 681-688, 2006 | 16 | 2006 |
| Modal analysis of conical shell filled with fluid MJ Jhung, JC Jo, KH Jeong Journal of mechanical science and technology 20, 1848-1862, 2006 | 14 | 2006 |
| CFD application to the regulatory assessment of FAC-caused CANDU feeder pipe wall thinning issue DG Kang, JC Jo Nuclear Engineering and Technology 40 (1), 37-48, 2008 | 12 | 2008 |
| Numerical prediction of a flashing flow of saturated water at high pressure JC Jo, JJ Jeong, BJ Yun, FJ Moody Nuclear Engineering and Technology 50 (7), 1173-1183, 2018 | 10 | 2018 |
| Fretting-wear characteristics of steam generator tubes by foreign object JJ Chull, JM Jo, CY Hwan, KH Jung, KT Hyung Nuclear Engineering and Technology 35 (5), 442-453, 2003 | 10 | 2003 |
| Assessment of the potential for fluidelastic instability of steam generator U-tubes in operating nuclear power plants JC Jo, WK Shin, SK Lee, WS Kim, HJ Kim, SJ Cho Transient thermal hydraulics, heat transfer, fluid-structure interaction …, 1994 | 10 | 1994 |
| A Study on the Thermal-hydraulic and Flow-induced Tube Vibration Analysis of Nuclear Steam Generators JC Jo, SK Lee, WS Kim, WK Shin, HY Kim, JT Ha Korea Institute of Nuclear Safety, Technical Report No. KINS/AR-198, 1992 | 10 | 1992 |
| Effects of a Venturi-Type Flow Restrictor on the Thermal-Hydraulic Response of the Secondary Side of a Pressurized Water Reactor Steam Generator to a Main Steam Line Break J Chull Jo, FJ Moody Journal of Pressure Vessel Technology 138 (4), 041304, 2016 | 9 | 2016 |
Dong Gu KangKorea Institute of Nuclear SafetyVerified email at kins.re.kr
