Team Member

Our Team

This is the team that struggles together to find out small pieces for making the big ideas real.

교수님PI

PI – HangJin Jo

– 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

Email contact: jhj04@postech.ac.kr

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.

Post-Doctoral Researcher

Taeyang Han

Condensation, water harvesting, nano/micro structure & wetting tailoring

Woo Hyun Jung

Boiling, nuclear safety, severe accident analysis

Ph.D. Candidate

Moonhee Choi

Boiling visualization & Nuclear thermal hydraulics

Joo won kang

Condensation, system code analysis

Minsu Kim

Printed Circuit Heat Exchangers(PCHE) & steam generator

Seung Gyu Seo

Boiling Numerical simulation

Tong Kyun Kim

Flow boiling on porous structured surfaces

Namhyeong Kim

Heat exchanger design, SFR & Nuclear thermal hydraulics

Mingyu Park

Optimized cooling channel development for nuclear fusion application

Eujae Kim

Leidenfrost for different surface conditions

Junghyeon Oh

Two phase visualization & Severe accident analysis

Jihwan Lim

Flow boiling, Hyper Vaportron channel optimization for nuclear fusion application

Don koan Hwang

Bubble coalescence & separation, research reactor safety

Chul Min Park

Pool boiling on porous structured surfaces

Hungyo Oh

Structural analysis for nuclear fusion cooling channel design, Lattice Boltzmann Method for boiling simulation

Seokyong Lee

Pool boiling analysis with surface modification

Yongnam Lee

Filmwise condensation for various conditions

Jae Hyun Choi

Turbomachinery design using CFD & Development of flow path for artificial olfactory system

Seong Min Shin

Numerical simulation for Printed Circuit Heat Exchanger (PCHE) optimization

Su Won Lee

System code development, Organic Rankine Cycle (ORC) layout design

UngJin Na

Lattice Boltzmann method for fluid flows

Seong Seok Chung

Numerical simulation for Printed Circuit Heat Exchanger (PCHE) optimization

sehyeon Park

Pool boiling analysis for porous structured surface

Taeil Kim

Chip cooling & Microchannel flow boiling

Seongkyun Jeong

N2 Brayton cycle

Myeonggi Cha

Filmwise condensation, Flow visualization with PIV

김지훈프로필-사진

Young Hyun Choi

Dropwise condensation on tailored surfaces, Flow visualization with PIV

Do Eun Kim

Freshman, 2021-1st semester

JiHun Kim

Freshman, 2021-1st semester

Gisu Lee

Freshman, 2021-1st semester

Jayoung Jeong

Freshman, 2021-1st semester

M.S. Candidate

Ceyda

Development of Reflood Model for System Code