Reactor Cooling Treatment Method After Steam Generator Heat Transfer Tube Broken Accident

Abstract

This proposal discloses a reactor cooling treatment method after a steam generator heat transfer tube rupture accident, the method is used in a pressurized water reactor to reduce the temperature and pressure of the reactor to a cold shutdown state after a steam generator heat transfer tube rupture accident occurs, The method includes the following steps in sequence: S1, terminating the fluid leakage between the primary circuit and the secondary circuit after the accident; S2, cooling the primary circuit with a steam generator in normal operation, and controlling the pressure of the primary circuit with a voltage stabilizer on the primary circuit. Perform depressurization; S3. When the pressure of the primary circuit is lower than the pressure of the secondary circuit, back-inject the working fluid on the secondary side of the damaged steam generator into the primary side of the steam generator, so as to further reduce the pressure and temperature of the primary circuit; S4. Connecting to the waste heat discharge system, so that the reactor reaches the cold shutdown condition. With this scheme, while realizing the temperature and pressure reduction after the SGTR accident, the release of radioactivity can be eliminated or minimized.

Description

technical field [0001] The invention relates to the technical field of pressurized water reactor accident response, in particular to a reactor cooling treatment method after a steam generator heat transfer tube rupture accident. Background technique [0002] After the rupture of the steam generator heat transfer tube in the pressurized water reactor nuclear power plant (SGTR, heat transfer tube rupture accident), the pressure of the primary circuit is much higher than that of the damaged steam generator (SG) (secondary side pressure), resulting in Leakage to the damaged SG caused loss of coolant in the primary circuit and increased radioactivity in the secondary circuit system. [0003] Under this accident, the existing accident handling method is as follows: the operator first identifies and isolates the damaged SG to limit the release of radioactivity, and after ensuring the supercooling degree and water content of the primary circuit, stop the safety injection system to s...

AI Technical Summary

Problems solved by technology

[0005] Aiming at the above-mentioned existing nuclear power plants usually use the steam generator blowdown or steam exhaust method for subsequent cooling and pressure reduction, but both of these two methods have the potential defect of expanding the range of radioactive release. This scheme provides a steam generator Reactor cooling treatment method after heat transfer tube failure accident. This method provides a new reactor cooling method for the unacceptable radioactive consequences that may be caused in the process of reducing the temperature and pressure of the reactor in the existing nuclear power plant. While lowering the temperature and pressure, it can prevent or minimize the release of radioactivity