RAPID COOLING SYSTEM AND METHOD FOR HIGH-TEMPERATURE GAS COOLED REACTOR NUCLEAR POWER STATION PRIMARY LOOP AFTER THERMAL TEST

摘要

A rapid cooling system and method for a high-temperature gas cooled reactor nuclear power station primary loop after a thermal test. The system comprises a reactor pressure vessel (1), a steam generator (2), a helium-water cooler (4), a gas-water separator (5), a helium compressor (6), an auxiliary steam pipeline (8), a first valve group (9), a second valve group (10), a high-pressure heater (12), a water-feeding pump (11), a fifth valve group (13), a steam-water separator (14), a condenser (18), a fourth valve group (16), a third valve group (15), and a waste liquid tank (17). According to the system and the method, the problem of an uncontrollable thermal test rate in a natural cooling process can be solved, and a cooling time period is shortened; moreover, a secondary side of the steam generator (2) can participate in the thermal test, so that the reliability of a secondary loop system is verified in advance; moreover, the secondary side pipeline of the steam generator (2) can be subjected to water vapor purging by utilizing the thermal test process, so that the secondary loop feed water quality is qualified.