Nuclear power station non-active engineering safety system

Abstract

The invention belongs to a nuclear power station safety system, and in particular relates to a nuclear power station non-active engineering safety system. The system comprises a secondary non-active residual heat removal exchanger, a steam condensation water tank, a non-active reactor cavity water injection system, a non-active high pressure reactor core water supplementing tank and related valves and pipelines. When a nuclear power station is in a design basis accident or a hyper design basis accident, a series of non-active and active safety devices are invested in steps, and a reactor primary circuit and a reactor core are timely, rapidly and effectively cooled, thus a nuclear power station smoothly enters into a safe cold shut-down amplifier state, a reactor disaster consequence is inhibited or alleviated, incident harm is reduced, and the safety of the nuclear power station is improved.

Description

technical field [0001] The invention belongs to nuclear power plant safety equipment, in particular to a nuclear power plant passive dedicated safety system. Background technique [0002] Passive means that the equipment or system is only driven by gravity, density, natural circulation and other natural phenomena, without introducing other power devices, which can greatly reduce the failure probability of equipment caused by power mechanical failure and improve the reliability of the safety system sex. [0003] The containment shell of a nuclear power plant is the fourth physical barrier of nuclear safety. Under certain accident conditions, it is necessary to prevent the failure of the containment sealing performance caused by excessive pressure in the containment. The usual method is to pass the safety spray pipeline on the top of the containment Spray into the containment space to condense or lower the temperature and pressure of the high-temperature water vapor or other ...

AI Technical Summary

Problems solved by technology

Except for Westinghouse AP1000 and AP600, which have a reactor cavity water injection system designed with built-in refueling water tanks, there are currently no reports on the design of special safety facilities for preventing pressure vessel melt-through in severe accident conditions for other reactor types.

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