Our Team
This is the team that struggles together to find out small pieces for making the big ideas real.
PI – HangJin Jo
Dr. HangJin Jo is an assistant professor in the Department of Mechanical Engineering and Division of Advanced Nuclear Engineering at Pohang University of Science and Technology (POSTECH). His research interests focus on exploring the underlying physics of thermal-hydraulics and extending the knowledge for advanced energy systems including nuclear power plant systems. His areas of expertise include experimental and analytical investigation on two-phase heat transfer (boiling and condensation), natural/forced two-phase flow development and radiation heat transfer. His research applies not only to general engineering problems but also to specific energy systems. e.g., nuclear power plant system. In a nuclear reactor, harsh environments (e.g., high pressure, high temperature, multi-components and two-phase flow) present unique and exciting challenges to thermal-hydraulic scientists and engineers for the development, testing, and characterization of current and future reactor systems. Therefore, Dr. Jo has extended the understanding of thermal-hydraulics for developing safer nuclear reactors and efficient energy systems.
Email contact: jhj04@postech.ac.kr
Assistant professor in Mechanical Engineering & Division of Advanced Nuclear Engineering at POSTECH (2019-current)
Assistant scientist in Engineering Physics & Nuclear Engineering at the University of Wisconsin-Madison (2017-2019)
Postdoc researcher in Engineering Physics & Nuclear Engineering at the University of Wisconsin-Madison (2015-2017)
Postdoc researcher at POSTECH (2013-2015)
Ph.D. in Mechanical Engineering at POSTECH, 2013
B.S. in Mechanical Engineering at POSTECH, 2008
Post-Doctoral Researcher
한태양
Taeyang Han
Condensation, water harvesting, nano/micro structure & wetting tailoring
정우현
Woo Hyun Jung
Boiling, nuclear safety, severe accident analysis
Ph.D. Candidate
최문희
Moonhee Choi
Boiling visualization & Nuclear thermal hydraulics
강주원
Joo won kang
Condensation, system code analysis
김민수
Minsu Kim
Printed Circuit Heat Exchangers(PCHE) & steam generator
서승규
Seung Gyu Seo
Boiling Numerical simulation
김동균
Tong Kyun Kim
Flow boiling on porous structured surfaces
김남형
Namhyeong Kim
Heat exchanger design, SFR & Nuclear thermal hydraulics
박민규
Mingyu Park
Optimized cooling channel development for nuclear fusion application
김의재
Eujae Kim
Leidenfrost for different surface conditions
오정현
Junghyeon Oh
Two phase visualization & Severe accident analysis
임지환
Jihwan Lim
Flow boiling, Hyper Vaportron channel optimization for nuclear fusion application
황돈관
Don koan Hwang
Bubble coalescence & separation, research reactor safety
박철민
Chul Min Park
Pool boiling on porous structured surfaces
오훈교
Hungyo Oh
Structural analysis for nuclear fusion cooling channel design, Lattice Boltzmann Method for boiling simulation
이석용
Seokyong Lee
Pool boiling analysis with surface modification
이용남
Yongnam Lee
Filmwise condensation for various conditions
최재현
Jae Hyun Choi
Turbomachinery design using CFD
& Development of flow path for artificial olfactory system
신성민
Seong Min Shin
Numerical simulation for Printed Circuit Heat Exchanger (PCHE) optimization
이수원
Su Won Lee
System code development, Organic Rankine Cycle (ORC) layout design
나웅진
UngJin Na
Numerical simulation for boiling heat transfer
정성석
sungsuk Jung
Numerical simulation for Printed Circuit Heat Exchanger (PCHE) optimization
박세현
sehyeon Park
Fabrication of porous structured surfaces & Analysis of pool boiling heat transfer performance
김태일
Taeil Kim
Chip cooling
Microchannel flow boiling
Basic
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Basic
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M.S. Candidate
차명기
Myeonggi Cha
Filmwise condensation, Flow visualization with PIV
최영현
Young Hyun Choi
Dropwise condensation on tailored surfaces, Flow visualization with PIV
정성균
Seongkyun Jeong
N2 Brayton cycle
김문현
Moonhyun Kim
Printed Circuit Heat Exchanger (PCHE) optimization
Ceyda Eldem
Development of Reflood Model for System Code