Thermal hydraulic performance assessment of dual-cooled annular nuclear fuel for OPR-1000 CH Shin, TH Chun, DS Oh, WK In Nuclear Engineering and Design 243, 291-300, 2012 | 76 | 2012 |
Effect of change in surface condition induced by oxidation on transient pool boiling heat transfer of vertical stainless steel and copper rodlets CY Lee, TH Chun, WK In International journal of heat and mass transfer 79, 397-407, 2014 | 69 | 2014 |
High-fidelity light water reactor analysis with the numerical nuclear reactor DP Weber, T Sofu, WS Yang, TJ Downar, JW Thomas, Z Zhong, JY Cho, ... Nuclear Science and Engineering 155 (3), 395-408, 2007 | 69 | 2007 |
A pressure drop model for spacer grids with and without flow mixing vanes TH Chun, DS Oh Journal of Nuclear Science and Technology 35 (7), 508-510, 1998 | 68 | 1998 |
Evaluation of a dual-cooled annular fuel heat split and temperature distribution YS Yang, CH Shin, TH Chun, KW Song Journal of nuclear science and technology 46 (8), 836-845, 2009 | 64 | 2009 |
Flow analysis for optimum design of mixing vane in a PWR fuel assembly WK In, DS Oh, TH Chun Nuclear Engineering and Technology 33 (3), 327-338, 2001 | 57 | 2001 |
Grid with nozzle-type coolant deflecting channels for use in nuclear reactor fuel assemblies HS Kang, KN Song, KH Yoon, YH Jung, TH Chun, DS Oh, WK In, JG Bang US Patent 6,130,927, 2000 | 53 | 2000 |
Numerical computation of heat transfer enhancement of a PWR rod bundle with mixing vane spacers WK In, TH Chun, CH Shin, DS Oh Nuclear Technology 161 (1), 69-79, 2008 | 43 | 2008 |
Fuel assembly spacer grid with swirl deflectors and hydraulic pressure springs TH Chun, DS Oh, WK In, KN Song, HS Kang, KH Yoon, DH Kim, JG Bang, ... US Patent 6,236,702, 2001 | 37 | 2001 |
High burnup fuel technology in Korea KW Song, YH Jeong, KS Kim, JG Bang, TH Chun, HK Kim, KN Song Nuclear Engineering and Technology 40 (1), 21, 2008 | 34 | 2008 |
Spacer grid for nuclear reactor fuel assemblies with grid springs maintaining conformal contact with fuel rods and enlarged elastic range KH Yoon, HS Kang, HK Kim, KN Song, YH Jung, TH Chun, DS Oh, WK In, ... US Patent 6,707,872, 2004 | 30 | 2004 |
An integral equation model for critical heat flux at subcooled and low quality flow boiling TH Chun, WP Baek, SH Chang Nuclear engineering and design 199 (1-2), 13-29, 2000 | 29 | 2000 |
Critical heat flux of oxidized zircaloy surface in saturated water pool boiling CY Lee, TH Chun, W Kee In Journal of Nuclear Science and Technology 52 (4), 596-606, 2015 | 27 | 2015 |
Spacer grid with hybrid flow-mixing device for nuclear fuel assembly T Chun, D Oh, W In, K Song, H Kim, H Kang, K Yoon, Y Jung US Patent 6,845,138, 2005 | 27 | 2005 |
Spacer grid with multi-springs and dimple vanes for nuclear fuel assemblies K Yoon, H Kang, K Song, YH Jung, T Chun, D Oh, W In US Patent 6,278,759, 2001 | 27 | 2001 |
Conceptual design of OPR-1000 compatible annular fuel assembly S Yong, M Kang, H Chang, H Tae, G Je, WS Kun | 26 | 2007 |
Empirical and computational pressure drop correlations for pressurized water reactor fuel spacer grids WK In, DS Oh, TH Chun Nuclear technology 139 (1), 72-79, 2002 | 26 | 2002 |
Simulation of turbulent flow in rod bundles using eddy viscosity models and Reynolds stress model WK In, DS Oh, TH Chun | 24 | 2003 |
Nuclear fuel spacer grid with dipper vanes HS Kang, KH Yoon, HK Kim, KN Song, YH Jung, TH Chun, DS Oh, WK In US Patent 6,421,407, 2002 | 24 | 2002 |
Spacer grid with H-spring for fuel rods for use in nuclear reactor fuel assemblies KH Yoon, HS Kang, HK Kim, KN Song, YH Jung, TH Chun, DS Oh, WK In US Patent 6,167,105, 2000 | 24 | 2000 |