G. W. Kim, G. C. Park, H. K. Cho, Scailing analysis for single-phase natural circulation under dynamic motion and its verification using MARS-KS code, Annals of Nuclear Energy, 159, 108308, 2021.
S. Y. Kim, D. H. Shin, C. S. Kim, G. C. Park, H. K. Cho, Computational fluid dynamics analysis of buoyancy-aided turbulent mixed convection inside a heated vertical rectangular duct, Progress in Nuclear Energy, 137, 103766, 2021.
J. S. Kim, H. K. Cho, Advanced boiling heat transfer model for a horizontal tube with numerical analysis of bubble behaviours, International Journal of Heat and Mass Transfer, 175, 121168, 2021.
S. Y. Kim, C. S. Kim, H. K. Cho, Local flow structure and turbulence quantities inside a heated rectangular riser in turbulent forced and mixed convection heat transfers, Experimental Thermal and Fluid Science, 122, 110297, 2021.
C. J. Choi and H. K. Cho, Effect of asymmetric airflow on liquid film behavior and emergency core coolant bypass in the downcomer geometry of a nuclear reactor pressure vessel. International Communications in Heat and Mass Transfer, 117, 104765, 2020.
J. S. Kim, Y. N. Kim, H. K. Cho, Predicting the sliding bubble velocity on the lower part of a horizontal tube heater under natural convection based on force balance analysis. International Journal of Heat and Mass Transfer, 151, 119453, 2020.
H. Y. Yoon, I. K. Park, J. R. Lee, S. J. Lee, Y. J. Cho, S. J. Do, H. K. Cho, J. J. Jeong, A Multiscale and Multiphysics PWR Safety Analysis at a Subchannel Scale. Nuclear Science and Engineering, 1-17, 2020.
J. H. Lee, H. K. Cho, G. C. Park, Three-dimensional looped network analysis code including core thermal analysis model for prismatic very high temperature gas-cooled reactor. International Journal of Thermal Sciences, 143, 76-91, 2019.
C. J. Choi and H. K. Cho, Investigation on emergency core coolant bypass with local measurement of liquid film thickness using electrical conductance sensor fabricated on flexible printed circuit board. International Journal of Heat and Mass Transfer, 139, 130-143, 2019.
H. K. Beom, G. W. Kim, G. C. Park, H. K. Cho, Verification and improvement of dynamic motion model in MARS for marine reactor thermal-hydraulic analysis under ocean condition. Nuclear Engineering and Technology, 51(5), 1231-1240, 2019.
D. H. Shin, S. Y. Kim, C. S. Kim, G. C. Park, H. K. Cho, Development of a heat transfer coefficient correlation for buoyancy-aided turbulent mixed convection of air inside a vertical channel. Applied Thermal Engineering, 159, 113884, 2019.
S. Y. Kim, D. H. Shin, C. S. Kim, G. C. Park, H. K. Cho, Flow visualization experiment in a two-side wall heated rectangular duct for turbulence model assessment in natural convection heat transfer. Nuclear Engineering and Design, 341, 284-296, 2019.
H. S. Choe, G. W. Kim, G. C. Park, H. K. Cho, K. H. Im, Application of the mesh adaptation technique to effective heat capacity method for melting simulation of the first wall in breeding blanket under high heat flux condition. Fusion Engineering and Design, 136, 891-896, 2018.
J. H. Yang, D. J. Euh, H. K. Cho, G. C. Park, Development of wall and interfacial friction models for two-dimensional film flow with local measurement methods. Nuclear Engineering and Design, 336, 141-153, 2018.
J. H. Lee, H. K. Cho, G. C. Park, Application of three-dimensional looped network analysis method to the core of prismatic very high temperature gas-cooled reactor. Annals of Nuclear Energy, 117, 12-24, 2018.
C. J. Choi, J. H. Yang, D. J. Euh, G. C. Park, H. K. Cho, Effect of wall friction model on predicting emergency core coolant behavior in upper downcomer with direct vessel safety injection using MARS-KS. Annals of Nuclear Energy, 116, 395-406, 2018.
J. Lee, G. C. Park, H. K. Cho, Simulation of wall film condensation with non-condensable gases using wall function approach in component thermal hydraulic analysis code CUPID. Journal of Mechanical Science and Technology, 32(3), 1015-1023, 2018.
S. J. Yoon, S. B. Kim, G. C. Park, H. Y. Yoon, H. K. Cho, Application of CUPID for subchannel-scale thermal–hydraulic analysis of pressurized water reactor core under single-phase conditions. Nuclear Engineering and Technology, 50(1), 54-67, 2018.
J.-H. Yang, C.-J. Choi, H.-K. Cho, D.-J. Euh, and G.-C. Park, Assessment of wall friction model in multi-dimensional component of MARS with air–water cross flow experiment, in Nuclear Engineering and Design, vol. 312, 2017.
G-W Kim, H-K Cho, G-C Park, Kihak Im, Melting and evaporation analysis of the first wall in a water-cooled breeding blanket module under vertical displacement event by using the MARS code, in Fusion Engineering and Design, vol. 118, 2017.
K. B. Lee, J. R. Kim, G. C. Park, H. K. Cho, Feasibility Test of a Liquid Film Thickness Sensor on a Flexible Printed Circuit Board Using a Three-Electrode Conductance Method, in Sensors, vol. 17(1), 2017.
Y-N Kim, J-S Kim, G-C Park, H-K Cho, Measurement of sliding bubble behavior on a horizontal heated tube using a stereoscopic image processing technique, in International Journal of Multiphase Flow, vol. 94, 2017.
D-H Shin, S-J Yoon, H-K Cho, G-C Park, T. Kim, Development of effective thermal conductivity models for Reserve Shutdown Control fuel block of prismatic HTGR for hydrogen production, in International journal of hydrogen energy, 2017.
D. H. Shin, C. S. Kim, G. C. Park, H. K. Cho, Experimental analysis on mixed convection in reactor cavity cooling system of HTGR for hydrogen production. International Journal of Hydrogen Energy, 42(34), 22046-22053, 2017.
G.-W. Kim, J.-H. Lee, H.-K. Cho, G.-C. Park, and K. Im, Development of thermal-hydraulic analysis methodology for multiple modules of water-cooled breeder blanket in fusion DEMO reactor, in Fusion Engineering and Design, vol. 103, 2016.
J.-H. Lee, H.-K. Cho, and G.-C. Park, Development of the loss coefficient correlation for cross flow between graphite fuel blocks in the core of prismatic very high temperature reactor-PMR200, in Nuclear Engineering and Design, vol. 307, 2016.
S-S Jeon, S-J Hong, H-K Cho, G-C Park, Development of Heat Transfer Model Package for Horizontal U-Shaped Heat Exchanger Submerged in Pool of Passive Safety System, in NUCLEAR TECHNOLOGY, vol. 196, 2016.
J.-H. Lee, S.-J. Yoon, H.-K. Cho, M. Jae, and G.-C. Park, Experimental investigation and CFD analysis on cross flow in the core of PMR200, in Annals of Nuclear Energy, vol. 83, 2015.
J.-H. Lee, I. W. Park, G.-W. Kim, G.-C. Park, H.-K. Cho, and K. Im, Thermal-hydraulic analysis of water cooled breeding blanket of K-DEMO using MARS-KS code, in Fusion Engineering and Design, vol. 98-99, 2015.
J. K. Suh, J. W. Kim, S. G. Kwon, J. Y. Lee, H. K. Cho, and G. C. Park, Experimental study of pressure drops through LOCA-generated debris deposited on a fuel assembly, in Nuclear Engineering and Design, vol. 289, 2015.
J.-H. Yang, H.-K. Cho, S. Kim, D.-J. Euh, and G.-C. Park, Experimental study on two-dimensional film flow with local measurement methods, in Nuclear Engineering and Design, vol. 294, 2015.
S.-S. Jeon, S.-J. Hong, H.-K. Cho, and G.-C. Park, Prediction of nucleate boiling heat transfer on horizontal U-shaped heat exchanger submerged in a pool of water using MARS code, in Nuclear Engineering and Design, vol. 295, 2015.
J. Lee, G.-C. Park, and H. K. Cho, Improvement of CUPID code for simulating filmwise steam condensation in the presence of noncondensable gases, in Nuclear Engineering and Technology, vol. 47, 2015.
D. H. Shin, S. J. Yoon, N. I. Tak, G. C. Park, and H. K. Cho, Analytical Study on the Effective Thermal Conductivity of Vhtr Fuel Block Geometry with Multiple Cylindrical Holes, in Nuclear Technology, vol. 191, Sep 2015.
H. K. Cho, Y. J. Cho, and H. Y. Yoon, Heat structure coupling of CUPID and MARS for the multi-scale simulation of the passive auxiliary feedwater system, in Nuclear Engineering and Design, vol. 273, 2014.
H. Y. Yoon, J. R. Lee, H. Kim, I. K. Park, C.-H. Song, H. K. Cho, et al., Recent Improvements in the Cupid Code for a Multi-Dimensional Two-Phase Flow Analysis of Nuclear Reactor Components, in Nuclear Engineering and Technology, vol. 46, 2014.
H. Kim, S. H. Kim, S.-J. Lee, I. K. Park, H. Y. Yoon, H. K. Cho, et al., Development of CUPID-SG for the analysis of two-phase flows in PWR steam generators, in Progress in Nuclear Energy, vol. 77, 2014.
H. Y. Yoon, J. J. Jeong, H. K. Cho, Y. S. Bang, and K. W. Seul, A multi-scale analysis of the transient behavior of an advanced safety injection tank, in Annals of Nuclear Energy, Vol. 62, December 2013.
H. K. Cho, S.-J. Lee, H. Y. Yoon, K.-H. Kang, and J. J. Jeong, Simulation of single- and two-phase natural circulation in the passive condensate cooling tank using the CUPID code, in Journal of Nuclear Science and Technology, vol. 50, 2013.
I. K. Park, H. Y. Yoon and H. K. Cho, Simulations of air-water flow and subcooled boiling flow using the CUPID code. Journal of Nuclear Science and Technology, 50(8), 813-827, 2013.