Control method for coping with feedwater flow loss accident of nuclear power plant
A technology of feed water flow and control method, applied in nuclear power generation, power plant safety devices, factory parameter adjustment, etc., can solve problems such as emergency shutdown failure, adverse accident consequences, rise in reactor coolant temperature and pressure, etc., and achieve a stable and safe state , to ensure integrity, the effect of advanced technical level
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Embodiment 1
[0037] The existing nuclear power plant system includes: reactor, steam generator (can be more than one), steam turbine, the steam generator conducts heat exchange with the reactor through the primary circuit, and the steam generator conducts heat exchange with the steam turbine through the secondary circuit, and the configuration of the steam generator There is auxiliary water supply, the secondary circuit is equipped with a feedwater isolation valve and a steam isolation valve, and the primary circuit is equipped with a safety injection system and a normal waste heat discharge system.
[0038] The control method of the invention for dealing with the loss of feedwater flow accident of a nuclear power plant includes an accident handling process and a safety monitoring process.
[0039] When the feedwater flow loss accident occurs, the water level of the steam generator will be low or the steam flow / feedwater flow will not match, and a corresponding alarm signal will be generate...
Embodiment 2
[0052] On the basis of embodiment 1, further technical scheme is:
[0053] ATWS response operations include: shut down the reactor through system control or manually, check that the steam turbine stops working, then start the auxiliary water supply system to supply water to the steam generator, inject boron-containing solution into the primary circuit, and control the temperature and pressure of the primary circuit to stabilize , The water level and pressure of the steam generator in the secondary circuit are stable.
[0054] Shutdown response operations include controlling the temperature stabilization of the primary circuit, controlling the water level of the pressurizer, controlling the pressure of the pressurizer, stabilizing the water level of the steam generator, and controlling the main steam bypass system to discharge steam and release heat. Through this series of operations Discharge the heat of the reactor, and control the temperature, pressure and water level of the...
Embodiment 3
[0059] The further technical solution on the basis of Embodiments 1 and 2 is: between confirming the shutdown and confirming the safety start, it also includes confirming that the power supply of the emergency safety bus is normal, so as to ensure that the specially designed safety facility system is available.
[0060] The safety monitoring process mainly monitors the subcriticality and the secondary side heat sink.
[0061] When entering the monitoring of important safety functions, the monitoring method for subcriticality is to measure the neutron flux and doubling period in real time. If the power in the power range is ≥ 5% or the doubling time in the middle range is ≥ 0, it means that the subcriticality has occurred If the event is lost, enter the ATWS response operation to recover the sub-criticality. When subcriticality is restored, return to the accident handling process to bring the reactor to a safe state.
[0062] If the feedwater flow rate of the auxiliary feedwat...
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