Research for nuclear power propulsion and energy production in the ocean
System design and phenomenon study considering dynamic motion in the ocean
-TH experiment under rolling and heaving
-Critical heat flux modeling for motion condition
-Flow characteristics under motion
-Dynamic motion modeling for MARS-KS
-Safety analysis of marine reactor under motion
-Physical models for motion conditions
-Subchannel analysis for the marine reactor under motion
-Multiphysics simulation using CUPID
Research about the microreactor for long-term, small and continuous power supply
-Multiple heat pipe experiment
-Mixed convection experiment
-Development of a new micro reactor concept
-Multiphysics simulation for a microreactor: Thermo-mechanical analysis coupled with Neutronics and fuel performance codes
-Thermo-mechanical analysis of heat pipe cooled microreactor using ANSYS and OpenFOAM
Research for analysis of various two-phase flows occurring in nuclear power systems
-Mechanistic modeling of boiling heat transfer
-Heat partitioning model for horizontal tube
-High precision liquid film measurement
-Simulation of coolant bypass using VOF
-Multi-scale simulation using MARS-CFD
-Passive safety system analysis
Nuclear Thermal-Hydraulic Engineering Laboratory
Seoul National University
1 Gwanak-ro, Gwanak-gu, Seoul 08826
Tel. 82-2-880-8339
Copyright © 2023 NuTHEL - All Rights Reserved.