Secondary side PRHR (Passive Residual Heat Removal) safety system of nuclear power station

Abstract

The invention provides a secondary side PRHR (Passive Residual Heat Removal) safety system of a nuclear power station. The secondary side PRHR safety system comprises a turbine, a draught fan, an aircooler and an emergent water supplementing tank, wherein a steam generator is respectively connected with the air cooler, the turbine and the emergent water supplementing tank through pipelines; output of the turbine drives the draught fan to cool the air cooler; connecting pipelines of the steam generator connected with the air cooler and the turbine are respectively provided with a first isolation valve and a second isolation valve; an outlet pipeline of the emergent water supplementing tank is provided with a third isolation valve and is then connected to the steam generator through a check valve after being connected with an outlet pipeline of the air cooler in parallel. According to the secondary side PRHR safety system provided by the invention, residual heat removal can be realizedunder the accident conditions of station blackout of the nuclear power station and reactor core residual heat removable disability; the whole process is operated in a passive way; air cooling equipment is utilized, so that potential safety hazard is reduced to the minimum; the potential safety hazard brought by a distribution way of a water tank in previous design is replaced, and meanwhile, thesecondary side PRHR safety system has the advantages of simple structure, convenience in distribution and the like.

Description

technical field [0001] The invention relates to a nuclear power plant waste heat discharge system, in particular to a nuclear power plant steam generator secondary side passive waste heat discharge system. Background technique [0002] After a power outage in the nuclear power plant, the main pump stopped working, the flow rate of the reactor coolant decreased rapidly, the water supply capacity of the secondary side of the steam generator decreased, and the heat generated by the core accumulated in the reactor coolant system, resulting in an increase in the temperature of the entire system . After a plant-wide power outage accident, whether the waste heat can be effectively discharged for a long time is related to the safety of the nuclear power plant. In the past, nuclear power plants only provided feed water to the secondary side of the steam generator through the pneumatic pump of the auxiliary feed water system under the accident condition of power failure. This kind o...

AI Technical Summary

Problems solved by technology

The passive system described in the above-mentioned patent documents discharges waste heat by setting up a water tank. Since the water tank layout has potential safety hazards, and the system does not completely use the passive method to discharge waste heat, the active system may not work normally. Condensation efficiency is low

Moreover, the direct use of water cooling in the early stage of the accident may cause the hidden danger that the residual heat of the core cannot be discharged in time.

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