2004 Ph. D. (Nuclear Thermal-Hydraulic), Department of Nuclear Engineering, SNU
2005 ~ 2013 Senior Researcher, Thermal-Hydraulic Safety Research Division, KAERI
2010 ~ 2011 Visiting Researcher, CEA-Grenoble, France
2013 ~ 2017 Assistant Professor, Department of Nuclear Engineering, SNU
2019 Visiting Researcher, ANL Illinois, USA
2017 ~ 2022 Associate professor, Department of Nuclear Engineering, SNU
2021 ~ Executive Editor of Nuclear Engineering and Technology
2022 ~ Professor, Department of Nuclear Engineering, SNU
1983 Ph. D. (Nuclear Thermal-Hydraulic), Department of Nuclear Engineering, RPI
1983 ~ 2017 Professor, Department of Nuclear Engineering, SNU
1997 ~ 2001 Advisor, Nuclear Safety and Security Commission
2002 ~ 2004 Director, Research Support Center, College of Engineering, SNU
2009 ~ 2010 President, Korea Nuclear Society
2010 ~ 2012 Vice President, Korea Institute of Science & Technology Evaluation and Planning
2012 ~ 2014 President, KEPCO International Nuclear Graduate School (KINGS)
2017 ~ Emeritus professor, Department of Nuclear Engineering, SNU
Experimental Investigation on Critical Heat Flux of Flow Boiling in an Annulus Channel under Heaving Conditions
Development of a Mean Bubble Size Approach to Improve Pool Scrubbing Swarm Rise Region Modeling
Development of robustness assessment methodology for passive safety system against potential performance degradation
Critical heat flux characteristics on a helical finned rod under the vertical, inclined and rolling conditions
Mixed convection heat transfer inside a rectangular riser in an air-cooled passive safety system
Experimental investigation of critical heat flux on a single heater rod under inclined and rolling conditions
Modelling of liquid film off-take in reactor vessel upper downcomer based on high-fidelity experiment and simulation
Development of mechanistic boiling heat partitioning model for horizontal tube under natural convection
Study on the buoyancy-aided turbulent mixed convection inside the vertical rectangular riser of VHTR RCCS
Experiment and analysis for improvement of crossflow loss coefficient for PMR200 Core
Experimental study for development of wall and interfacial friction models in two-dimensional film flow
Development of heat transfer model for horizontal u-shaped heat exchanger submerged in pool
Experiment on critical heat flux under rolling condition for TAPINS-M code development
Thermal-hydraulic analysis of a floating nuclear reactor under ocean conditions using MARS-KS moving reactor model
Coupling between subchannel module of CUPID and fuel code FINIX for multi-physics transient analysis of PWR core
Thermal-structural analysis of micro reactor core using coupled OpenFOAM and heat pipe code
Implementation of multi-dimensional flow analysis capability in MARS-KS motion model
for marine reactor safety analysis
Establishment and validation of reactor core simulator for subchannel thermal-hydraulic and neutron transport coupled analysis
Improvement of grid-directed cross flow in CUPID subchannel scale analysis module based on CFD calculation
Numerical simulation of structure phase change under high heat flux condition coupled with nuclear system analysis code
Improvement of dynamic motion model in MARS-KS for marine reactor thermal-hydraulic analysis
Improvement of subchannel scale analysis capability of CUPID with grid-directed cross flow and fuel rod models
Experimental measurement and force balance analysis of sliding vapor bubble behavior on a horizontal tube
Extension of the component thermal-hydraulics analysis code CUPID toward sub-channel scale analysis of PWR reactor core
Development of three-ring conductance sensor based on FPCB for measuring liquid film thickness under non-isothermal condition
Enhancement and optimization on cooling performance of gas-based fusion reactor blanket using binary and ternary gas mixtures
Nuclear Thermal-Hydraulic Engineering Laboratory
Seoul National University
1 Gwanak-ro, Gwanak-gu, Seoul 08826
Tel. 82-2-880-8339
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