Nuclear Safety Research Center (NSRC)
Accident Response Analysis Research Center
Advanced Research Center for Nuclear Excellence
Center for Containment Thermal-Hydraulics Research for Nuclear Power Plant Passive Safety
Research on the condensation and boiling heat transfer phenomena under natural circulation conditions for Passive Containment Cooling System (PCCS) performance analysis
Enabling a compact design of PCCS for operating nuclear power plants
Carrying out experimental investigations and developing computational analysis methods for PCCS design and evaluation
2017.09. ~ 2022.08.
1st Project (CAU)
A study on steam condensation phenomena at the exterior surface of a tube bundle for operating NPP containment conditions.
2nd Project (INU)
Research on the boiling-assisted flow under natural convection conditions in a tube bundle geometry.
3rd Project (KAERI)
Computational model development to analyze containment thermal-hydraulic phenomena under natural convection conditions.
Major Research Items
Passive cooling system to mitigate containment over-pressurization during severe accident, utilizing natural heat transfer and fluid dynamics
Component of PCCS
PCCX : Heat exchanger inside the containment
PCCT : Heat sink outside of the containment
Natural circulation loop between PCCX and PCCT