Selected international journal papers and conference proceedings
2022
Improvement of Entrainment Model for Horizontal Flow in ATHLET and Application to Mantilla Experiment and TPTF
Jaejin Lee, Markus Junk, Tomasz Skorek, and Philipp Josef Schöffel
Nuclear Engineering and Design
Improved correlation of liquid entrainment fraction in horizontal pipes
Jaejin Lee, Markus Junk, Tomasz Skorek, and Philipp Josef Schöffel
Nuclear Engineering and Design
Convergence analysis of fixed-point iteration with Anderson Acceleration on a simplified neutronics/thermal-hydraulics system
Jaejin Lee and Han Gyu Joo
Nuclear Engineering and Technology
2019
Development of a Drift-Flux Model Based Core Thermal-Hydraulics Code for Efficient High-Fidelity Multiphysics Calculation
Jaejin Lee, Alberto Facchini, and Han Gyu Joo,
Nuclear Engineering and Technology
2025
Sensitivity Analysis of Initial Flow Rate for Startup of Inactive Reactor Coolant Pumps in SMR with Natural Circulation
Jaejin Lee, Doyoung Shin, Joonsoo Park, Chi-Jin Choi
Trans. of the Korean Nuclear Society Spring Meeting, Jeju, Korea
2022
Improvement of Entrainment Model for Horizontal Flow in ATHLET and Application to Mantilla Experiment and TPTF
Jaejin Lee, Markus Junk, Tomasz Skorek, and Philipp Josef Schöffel
NURETH-19, Brussels, Belgium
2019
Initial Assessment of Anderson Acceleration on Pinwise Coupled Neutronics/Thermal-Hydraulics Code nTER/ESCOT
Jaejin Lee, Jin Young Cho, and Han Gyu Joo
Procs. of the Reactor Physics Asia (RPHA19), Osaka, Japan
Radial and Axial Domain Decomposition of a Core Thermal-Hydraulics Code for Massively Parallel Computing Platforms
Jaejin Lee, Alberto Facchini, and Han Gyu Joo
Trans. of Korea Nuclear Society Spring Meeting, Jeju, Korea
2018
Application of the MARS-LMR/FREK Spatial Kinetics Coupled System Code to Stability Analyses of the Prototype Sodium Cooled Fast Reactor
Jaejin Lee, Jong Hyuck Won, Min Jae Lee, Jae-Yong Lim, and Han Gyu Joo
PHYSOR 2018, Cancun, Mexico
2016
Preliminary Development of a Drift-Flux Model Based Pin-Resolved Core Thermal-Hydraulics Code for Dedicated Use in Efficient High-Fidelity Neutronics Coupled Calculation
Jaejin Lee and Han Gyu Joo
Trans. of American Nuclear Society Winter Meeting, Las Vegas, NV, USA,
2015
nTRACER/COBRA-TF Coupling and Initial Assessment
Jaejin Lee, Yann Perin, Kiril Velkov, and Han Gyu Joo
Trans. of Korea Nuclear Society Spring Meeting, Jeju, Korea