When a station blackout accident occurs, the decay heat of AC600/1000 reactor core can be removed to the atmosphere as the ultimate heat sink through natural circulation flows established by the primary coolant loop, the secondary side cycle of SG and air cycle
respectively. Nuclear Power Institute of China (NPIC) has built a passive emergency residual heat removal (ERHR) experiment facility in order to research the natural circulation flow characteristics for AC600/1000 ERHR system and to verify the computer code ERHRAC. The

facility parameters are as the following:

Heating power: 80-400 kW

Design pressure in the secondary side of SG: 8.6 MPa

Elevation difference between air cooler and SG: 7.2 m

Equivalent diameter of chimney: 0.7 m

Height of chimney: 12 m

The core make-up water tanks are used in the design of AC600/1000 so as to eliminate the high-pressure safety injection pumps and increase reliability of the safety system. The function characteristics and coolant flow transient of core make-up water tank, accumulator and automatic depressurization system can be tested using NPIC core make-up water tank experiment facility to simulate a small LOCA. The facility parameters are as the following:

Design pressure:

Design temperature:

Core make-up tank volume: Accumulator volume:

RPV volume:

Pressurizer volume:

Break sizes: