Reactor cooling treatment method after steam generator heat transfer pipe breakage accident

Abstract

The invention discloses a reactor cooling treatment method after a steam generator heat transfer pipe breakage accident. The method is used for cooling and depressurizing a reactor to a cold shut-downstate after a steam generator heat transfer tube rupture accident occurs in a pressurized water reactor, and sequentially comprises the following steps: S1, stopping fluid leakage between a primary loop and a secondary loop after the accident, S2, cooling the primary loop by using a normally working steam generator, and reducing the pressure of the primary loop by using a pressure stabilizer on the primary loop, S3, when the pressure of the primary loop is lower than that of the secondary loop, reversely injecting a working medium on the secondary side of the damaged steam generator into theprimary side of the steam generator to further reduce the pressure and the temperature of the primary loop, and S4, connecting a residual heat removal system to enable the reactor to reach a cold shut-down working condition. By the adoption of the scheme, after an SGTR accident, cooling and pressure reduction are achieved, and meanwhile radioactive release can be eradicated or reduced to the minimum.

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