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Offshore Nuclear Reactor

Research for nuclear power propulsion and energy production in the ocean

System design and phenomenon study considering dynamic motion in the ocean

Experimental study

-TH experiment under rolling and heaving 

-Critical heat flux modeling for motion condition 

-Flow characteristics under motion 

Safety analysis

-Dynamic motion modeling for MARS-KS  

-Safety analysis of marine reactor under motion 

-Physical models for motion conditions

High fidelity simulation

-Subchannel analysis for the marine reactor under motion 

-Multiphysics simulation using CUPID

Special Purpose Microreactor

Research about the microreactor for long-term, small and continuous power supply

Experimental study

-Multiple heat pipe experiment 

-Mixed convection experiment 

-Development of a new micro reactor concept 

High fidelity simulation (TH-Neutronics)

-Multiphysics simulation for a microreactor: Thermo-mechanical analysis coupled with Neutronics and fuel performance codes

High fidelity simulation (TH-Solid mechanics)

-Thermo-mechanical analysis of heat pipe cooled microreactor using ANSYS and OpenFOAM 

Two-phase CFD & modeling

Research for analysis of various two-phase flows occurring in nuclear power systems

Two-phase flow modeling

-Mechanistic modeling of boiling heat transfer 

-Heat partitioning model for horizontal tube

High fidelity measurement and simulation

-High precision liquid film measurement 

-Simulation of coolant bypass using VOF

Safety analysis

-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


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