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Professor

Hyoung Kyu Cho

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

Emeritus Professor

Goon-Cherl Park

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  

Researchers

Moonhee Choi

Jangkeun Park

Jangkeun Park

Jangkeun Park

Jangkeun Park

Jangkeun Park

Ph.D. Students

Chang Won Lee

Chang Won Lee

Chang Won Lee

San Lee

Chang Won Lee

Chang Won Lee

Jin-Seong Yoo

Chang Won Lee

Myung Jin Jeong

Myung Jin Jeong

Myung Jin Jeong

Myung Jin Jeong

Jiwon Ahn

Myung Jin Jeong

Jiwon Ahn

MS students

Hyung-Joo Seo

Hyung-Joo Seo

Hyung-Joo Seo

Heepyo Hong

Hyung-Joo Seo

Hyung-Joo Seo

Hyukjae Ko

Hyung-Joo Seo

Yeonghun Lee

Yeonghun Lee

Yeonghun Lee

Yeonghun Lee

Jahyun Ku

Yeonghun Lee

Jahyun Ku

Part-time student

Je-hee Lee

Ga-eul Choi

Ga-eul Choi

Ga-eul Choi

Ga-eul Choi

Ga-eul Choi

Erol Bicer

Sungwon Lim

Sungwon Lim

Sungwon Lim

Sungwon Lim

Sungwon Lim

Ph.D. Alumni (Thesis)

Sin-Yeob Kim (2022)

Mixed convection heat transfer inside a rectangular riser in an air-cooled passive safety system

Geon-Woo Kim (2021)

Experimental investigation of critical heat flux on a single heater rod under inclined and rolling conditions

Chi-Jin Choi (2021)

Modelling of liquid film off-take in reactor vessel upper downcomer based on high-fidelity experiment and simulation

Jae Soon Kim (2020)

Development of mechanistic boiling heat partitioning model for horizontal tube under natural convection 

Dong-Ho Shin (2018)

Study on the buoyancy-aided turbulent mixed convection inside the vertical rectangular riser of VHTR RCCS 

Jeong-Hun Lee (2017)

Experiment and analysis for improvement of crossflow loss coefficient for PMR200 Core 

Jin-Hwa Yang (2016)

Experimental study for development of wall and interfacial friction models in two-dimensional film flow 

Seong-Su Jeon (2015)

Development of heat transfer model for horizontal u-shaped heat exchanger submerged in pool 

Jin Seok Hwang (2013)

Experiment on critical heat flux under rolling condition for TAPINS-M code development 

MS. Alumni (Thesis)

Jangkeun Park (2021)

Coupling between subchannel module of CUPID and fuel code FINIX for multi-physics transient analysis of PWR core

Myung Jin Jeong (2021)

Thermal-structural analysis of micro reactor core using coupled OpenFOAM and heat pipe code

Sang Wook Park (2021)

Implementation of multi-dimensional flow analysis capability in MARS-KS motion model 

for marine reactor safety analysis

Youyeon Choi (2020)

Establishment and validation of reactor core simulator for subchannel thermal-hydraulic and neutron transport coupled analysis 

Jae-Ho Lee (2019)

Improvement of grid-directed cross flow in CUPID subchannel scale analysis module based on CFD calculation 

Hee Su Choe (2019)

Numerical simulation of structure phase change under high heat flux condition coupled with nuclear system analysis code 

Hee-Kwan Beom (2019)

Improvement of dynamic motion model in MARS-KS for marine reactor thermal-hydraulic analysis 

Seul-Been Kim (2018)

Improvement of subchannel scale analysis capability of CUPID with grid-directed cross flow and fuel rod models 

Yu-Na Kim (2017)

Experimental measurement and force balance analysis of sliding vapor bubble behavior on a horizontal tube 

Seok Jong Yoon (2017)

Extension of the component thermal-hydraulics analysis code CUPID toward sub-channel scale analysis of PWR reactor core 

Kyu Byung Lee (2016)

Development of three-ring conductance sensor based on FPCB for measuring liquid film thickness under non-isothermal condition  

Il-Woong Park (2013)

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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