Team Member

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


Alumni