A coolant bypass flow control method and leak tightness test device for a high-temperature gas cooled reactor. The coolant bypass flow leak tightness test device for a high-temperature gas cooled reactor comprises a reactor unit (100), which comprises a protective layer (101) and a plurality of groups of graphite blocks (102); a blocking unit (200), which comprises longitudinal sealing members (201) and transverse sealing racks (202); and an adjusting unit (300), which comprises a plurality of rotating rods (301), a transmission member (302) which is arranged on one side of the rotating rods, and a limiting cover (303). Testing of the leak tightness is conducted by means of a simulation experiment device, and the longitudinal bypass flow and transverse leakage flow of a helium coolant are blocked, thereby reducing the effect of structural bypass flow on the flow distribution of the helium coolant within a pebble bed, ensuring an effective flow rate of the coolant flowing through the pebble bed, and thus optimizing the temperature distribution within the pebble bed and the maximum temperature of fuel, thereby providing support for the design and justification of the reactor structure of the high-temperature gas cooled reactor, further improving the safety and reliability of the pebble bed high-temperature gas cooled reactor.
- 출원번호 : CN2024/105275
- 출원인 : HUANENG NUCLEAR ENERGY DESIGN AND RESEARCH INSTITUTE CO., LTD
- 특허번호 :
- IPC : G21C-013/028(2006.01)