In order to research the performance of Passive Containment Cooling System (PCS) and verify the containment safety of AP/CAP series pressurized water reactor nuclear power plants (NPPs), an integral test facility for PCS (short name CERT) is designed and constructed in China. In this paper, the CERT test facility is modeled using the T-H program GASFLOW. The steel containment shell and internals, including compartments, flow paths between compartments and heat sinks are considered. The thermal hydraulic response of the facility under scaled mass and energy release of LOCA is studied.