CN109098788B - Pressurized water reactor nuclear power unit overspeed protection control optimization system and optimization control method - Google Patents

Pressurized water reactor nuclear power unit overspeed protection control optimization system and optimization control method Download PDF

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CN109098788B
CN109098788B CN201810766074.4A CN201810766074A CN109098788B CN 109098788 B CN109098788 B CN 109098788B CN 201810766074 A CN201810766074 A CN 201810766074A CN 109098788 B CN109098788 B CN 109098788B
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pressurized water
water reactor
power unit
reactor nuclear
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CN109098788A (en
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文立斌
李俊
孙艳
张翌晖
刘光时
雷亭
吴健旭
卢万里
廖卫国
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Electric Power Research Institute of Guangxi Power Grid Co Ltd
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    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
    • F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
    • F01D21/00—Shutting-down of machines or engines, e.g. in emergency; Regulating, controlling, or safety means not otherwise provided for
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
    • F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
    • F01D17/00—Regulating or controlling by varying flow
    • F01D17/10—Final actuators
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
    • F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
    • F01D17/00—Regulating or controlling by varying flow
    • F01D17/20—Devices dealing with sensing elements or final actuators or transmitting means between them, e.g. power-assisted
    • F01D17/22—Devices dealing with sensing elements or final actuators or transmitting means between them, e.g. power-assisted the operation or power assistance being predominantly non-mechanical
    • F01D17/24—Devices dealing with sensing elements or final actuators or transmitting means between them, e.g. power-assisted the operation or power assistance being predominantly non-mechanical electrical

Abstract

The invention relates to the technical field of control of a pressurized water reactor nuclear power unit, in particular to an overspeed protection control optimization system and an overspeed protection control optimization method for the pressurized water reactor nuclear power unit. The invention controls the pressurized water reactor nuclear power unit, can quickly eliminate the rotating speed fault of the pressurized water reactor nuclear power unit and eliminate the potential safety hazard of a steam turbine of the nuclear power unit.

Description

Pressurized water reactor nuclear power unit overspeed protection control optimization system and optimization control method
Technical Field
The invention relates to the technical field of control of a pressurized water reactor nuclear power unit, in particular to an overspeed protection control optimization system and an overspeed protection control optimization method for the pressurized water reactor nuclear power unit.
Background
In the operation process of a steam turbine of a large-scale unit, Overspeed Protection Control (OPC) is the first line of defense for high-frequency Protection of the unit. The overspeed of the steam turbine is often represented as the flying rise of the unit rotating speed when the electric load is reduced, and the OPC reduces the mechanical power output by the unit through the quick closing of a high-pressure valve and a middle-pressure valve in the steam turbine so as to limit the over-quick rise of the unit rotating speed. The quick closing action of the OPC on the steam valve is disturbance similar to a step signal for the steam turbine to some extent, and negative effects in other aspects can be brought while the rotating speed is restrained from exceeding the limit, so that the protection action of the OPC on the unit overspeed needs to be subjected to multi-aspect simulation verification.
The OPC protection effect is not only limited to thermal power generating units, but also has great significance for protecting nuclear power generating units. Compared with a thermal power generating unit, the flash evaporation amount of residual wet steam in a steam turbine of the nuclear power generating unit is higher, the unit is easier to overspeed, and the adaptability of a nuclear reactor to load is poorer. In order to prevent the nuclear power generating unit from overspeed and even stopping during the grid fault, which causes a wider range of accidents, OPC protection is necessary to be arranged in the nuclear power generating unit. At present, most thermal power generating units in China are provided with OPC protection devices with mature technologies and theories, and in nuclear power generating units, a reasonable OPC scheme and the dynamic characteristics of the system under the action of the OPC scheme are not verified in a simulation mode. At present, the proportion of the nuclear power generation capacity in the power grid in China is increasing day by day, the requirements on higher safety and stability of the operation of a nuclear power unit are met, and the research of OPC (optical proximity correction) has the necessity for protecting the nuclear power unit.
Disclosure of Invention
According to the traditional OPC principle, the protection action of the nuclear power station can be triggered by rotating speed deviation and power deviation; the action of the valve can act on the high-pressure valve and can also act on the high-pressure valve and the medium-pressure valve simultaneously. According to the different OPC triggering modes and the different valve closing modes, the invention provides an overspeed protection control optimization system and an optimization control method for a pressurized water reactor nuclear power unit, and the specific technical scheme is as follows:
the system comprises a trigger signal acquisition module, a logic judgment module and a valve closing signal generation module, wherein the trigger signal acquisition module is connected with a speed regulator and a power grid side of the nuclear power unit and used for acquiring a trigger signal; the trigger signals comprise power deviation and rotating speed deviation of a power system in which the pressurized water reactor nuclear power unit and the pressurized water reactor nuclear power unit are located and high-frequency generator tripping signals of the pressurized water reactor nuclear power unit; the logic judgment module is respectively connected with the trigger signal acquisition module and the valve closing signal generation module and is used for judging according to the trigger signal acquired by the trigger signal acquisition module and giving a valve quick closing instruction to the valve closing signal generation module; the steam valve closing signal generating module is connected with a steam turbine of the nuclear power unit and used for receiving a steam valve quick closing instruction of the logic judging module and outputting a signal to control quick closing of a high-pressure steam valve and a medium-pressure steam valve of the steam turbine of the pressurized water reactor nuclear power unit.
The optimization control method of the pressurized water reactor nuclear power unit overspeed protection control optimization system comprises the following steps:
(1) the trigger signal acquisition module acquires a trigger signal from the speed regulator; the trigger signals comprise power deviation and rotating speed deviation of a power system in which the pressurized water reactor nuclear power unit and the pressurized water reactor nuclear power unit are located and high-frequency generator tripping signals of the pressurized water reactor nuclear power unit;
(2) the logic judgment module judges whether a high-frequency cutting machine signal of the pressurized water reactor nuclear power unit is 1, if so, a valve quick closing instruction is immediately given to the valve closing signal generation module, and the valve closing signal generation module outputs a signal to control quick closing of a high-pressure valve and a medium-pressure valve of a pressurized water reactor nuclear power unit steam turbine;
(3) when the logic judgment module judges that the high-frequency cutting machine signal of the pressurized water reactor nuclear power unit is 0, the logic judgment module continuously judges whether the power deviation is greater than or equal to a set value, if the logic judgment module judges that the power deviation is greater than or equal to the set value, a valve quick-closing instruction is immediately given to a valve closing signal generation module, and the valve closing signal generation module outputs a signal to control a high-pressure valve and a medium-pressure valve of a pressurized water reactor nuclear power unit steam turbine to be quickly closed;
(4) when the logic judgment module judges that the high-frequency cutting machine signal of the pressurized water reactor nuclear power unit is 0 and the power deviation is smaller than a set value, the logic judgment module continuously judges whether the rotating speed deviation is larger than or equal to the set value or not, if the logic judgment module judges that the rotating speed deviation is larger than or equal to the set value, a valve quick closing instruction is immediately given to a valve closing signal generation module, and the valve closing signal generation module outputs a signal to control a high-pressure valve of a turbine of the pressurized water reactor nuclear power unit to be quickly closed;
(5) and when the logic judgment module judges that the high-frequency generator tripping signal of the pressurized water reactor nuclear power unit is 0, the power deviation is smaller than a set value and the rotating speed deviation is smaller than the set value, the pressurized water reactor nuclear power unit overspeed protection control system quits operation, and the speed regulator plays a role in regulating the rotating speed of the steam turbine again.
Preferably, the power deviation is the difference between the mechanical power output by the pressurized water reactor nuclear power unit and the electromagnetic power output by the pressurized water reactor nuclear power unit to the power grid side; the rotating speed deviation is the difference between the rotating speed of a steam turbine of the pressurized water reactor nuclear power unit and the rated rotating speed.
Preferably, the set value of the power deviation is 30% per unit.
Preferably, the set value of the rotational speed deviation is 3% per unit.
The invention has the beneficial effects that: the invention provides an overspeed protection control optimization system and an overspeed protection control optimization method for a pressurized water reactor nuclear power unit. The invention controls the pressurized water reactor nuclear power unit, can quickly eliminate the rotating speed fault of the pressurized water reactor nuclear power unit and eliminate the potential safety hazard of a steam turbine of the nuclear power unit.
Drawings
FIG. 1 is a schematic diagram of a general pressurized water reactor nuclear power plant model;
FIG. 2 is a schematic diagram of a pressurized water reactor nuclear power plant model with an overspeed protection control optimization system for a pressurized water reactor nuclear power plant according to the present invention;
FIG. 3 is a schematic diagram of the principle of the optimization control method of the pressurized water reactor nuclear power unit overspeed protection control optimization system in the invention;
FIG. 4 is a logic diagram of an optimization control method of the pressurized water reactor nuclear power unit overspeed protection control optimization system according to the present invention;
FIG. 5 is a waveform of the ramp up of the rotational speed of the nuclear power plant of the pressurized water reactor without the effect of the overspeed protection control system in an embodiment of the present invention;
FIG. 6 is a waveform of the ramp up of the rotational speed of a nuclear power plant of the pressurized water reactor under the influence of an existing overspeed protection control system in an embodiment of the present invention;
fig. 7 is a waveform diagram of the flying rise of the rotating speed of the piezoreactor nuclear power unit under the action of the overspeed protection control optimization system for the piezoreactor nuclear power unit in the embodiment of the invention.
Detailed Description
For a better understanding of the present invention, reference is made to the following detailed description taken in conjunction with the accompanying drawings in which:
as shown in fig. 1, the pressurized water reactor nuclear power plant is a general pressurized water reactor nuclear power plant model, and includes a primary loop model and a secondary loop model. The two-loop model of the pressurized water reactor nuclear power unit comprises a steam turbine speed regulating system and a steam turbine, the steam turbine speed regulating system comprises a speed regulator, the speed regulator adopts a power-frequency electro-hydraulic speed regulator model and comprises a rotating speed measuring unit, a rotating speed regulator, a power measuring unit, an electro-hydraulic converter, a relay and a hydraulic motor, the rotating speed measuring unit and a power measuring unit of the speed regulator respectively obtain a rotating speed deviation signal and a power deviation signal of the pressurized water reactor nuclear power unit, and the electro-hydraulic converter converts corresponding electric signals of the rotating speed deviation signal and the power deviation signal into hydraulic signals to enable the relay and the hydraulic motor to act, so that the purpose of regulating a steam valve of the steam turbine; the steam turbine is a simplified model that takes into account the volumetric effects of the high pressure steam and the intermediate reheat steam. The system comprises a pressurized water reactor nuclear power unit, a nuclear reactor, a steam generator, a reactor power control system, a coolant circulation system and a control system, wherein the primary circuit of the pressurized water reactor nuclear power unit comprises a nuclear reactor, a reactor power control system, a coolant circulation system and a steam generator, and the nuclear reactor comprises a neutron dynamic model, reactor core fuel and a coolant heat transfer model; the coolant circulating system comprises a cold wire temperature model, a hot wire temperature model, a primary circuit average temperature model and a main pump model; the steam generator includes a steam generator model. According to the physical characteristics of each link, the incremental equation according to which a loop of the pressurized water reactor nuclear power unit model is modeled is as follows:
the incremental equation for the reactor power control system is as follows:
Δρ(t)＝αρΔρext+αFΔTF+αc(ΔTθ1+ΔTθ2)/2； ①
Figure BDA0001729059790000031
incremental equation for nuclear reactor:
Figure BDA0001729059790000032
Figure BDA0001729059790000033
incremental equation of coolant circulation system driven by coolant main pump:
Figure BDA0001729059790000041
Figure BDA0001729059790000042
Figure BDA0001729059790000043
Figure BDA0001729059790000044
Figure BDA0001729059790000045
incremental equation for steam generator:
Figure BDA0001729059790000046
Figure BDA0001729059790000047
Figure BDA0001729059790000048
in the formula: Δ ρ (t) represents the increase in reactivity of the nuclear reactor; alpha is alphaρIs effective delayed neutron fraction; alpha is alphaFIs the fuel temperature feedback coefficient; alpha is alphacIs the coolant temperature feedback coefficient; Δ ρextRepresents the bar set reactivity increment; delta TFRepresenting core temperature increase; delta Tθ1Representing the temperature increment of the coolant at the core inlet end; delta Tθ2Representing the temperature increment of the coolant at the outlet end of the core; delta TavRepresents the coolant average temperature increase; Δ n (t) and Δ n represent the increase in neutron flux in the nuclear reaction; lambda is the decay constant of the equivalent single-group delayed neutron precursor nucleus; Δ c (t) represents the increase in density of the delayed neutron precursor nuclei; l*Is the neutron mean life; beta is the effective delayed neutron fraction; delta TFAn increase in core temperature; f is the percentage of the reactor core power occupied by the reactor core temperature rise; m isFIs the mass of the fuel; c. CPFIs the specific heat capacity of the fuel; h represents a heat transfer coefficient between the fuel and the coolant in the core; p0Representing the initial nuclear power of the reactor; a represents a heat transfer area between fuel and coolant in the core; m isCRepresenting the coreThe mass of the coolant; c. CPCRepresents the specific heat capacity of the coolant in the core;
Figure BDA0001729059790000049
representing the rate of coolant flow through the core; delta THLRepresents the hot wire temperature increase; delta TCLRepresents the cold line temperature increase; delta TPDeviation of average temperature of coolant at steam generator; tau isHLIs the hot-wire volume time constant; tau isCLIs the cold line volume time constant; delta TmRepresenting the temperature deviation of the metal U-shaped pipe; delta PSRepresenting a two-circuit steam pressure deviation; Δ μ represents a valve opening degree deviation; tau isPRepresenting a time constant of the coolant in the steam generator; tau ismRepresents the time constant of the U-shaped tube; tau ispsRepresents the time constant of the steam in the two loops; k is a radical ofpmRepresents the temperature coefficient of the metal tube; k is a radical ofpcRepresents a hot-wire temperature coefficient; k is a radical ofmpRepresents a coolant temperature coefficient; k is a radical ofmsRepresents a pressure temperature coefficient; k is a radical ofpsmRepresents the pressure coefficient of the metal pipe; k is a radical ofpsyRepresenting the valve pressure coefficient.
The system comprises a trigger signal acquisition module, a logic judgment module and a valve closing signal generation module, wherein the trigger signal acquisition module is connected with a speed regulator and a power grid side of the nuclear power unit and used for acquiring a trigger signal; the trigger signals comprise power deviation and rotating speed deviation of a power system in which the pressurized water reactor nuclear power unit and the pressurized water reactor nuclear power unit are located and high-frequency generator tripping signals of the pressurized water reactor nuclear power unit; the logic judgment module is respectively connected with the trigger signal acquisition module and the valve closing signal generation module and is used for judging according to the trigger signal acquired by the trigger signal acquisition module and giving a valve quick closing instruction to the valve closing signal generation module; the valve closing signal generating module is connected with a steam turbine of the nuclear power unit and used for receiving a valve quick closing instruction of the logic judging module and outputting a signal to control quick closing of a high-pressure valve and a medium-pressure valve of the steam turbine of the pressurized water reactor nuclear power unit.
As shown in FIG. 2, the present invention provides a User-defined module (User D) in a power system analysis integration program (PSASP)effective modeling, UDM) establishes a model of a pressurized water reactor nuclear power unit with the overspeed protection control optimization system of a pressurized water reactor nuclear power unit. The modeling parameters are shown in Table 1 below, where hr represents hours, ft2Expressed in square feet, F is a unit of temperature and represents degrees fahrenheit.
TABLE 1 modeling parameters for a pressurized water reactor nuclear power plant model
Figure BDA0001729059790000051
Figure BDA0001729059790000061
As shown in FIG. 3, wherein FHPIs the proportion of the output of the high-pressure cylinder, FIPIs the proportion of the output of the intermediate pressure cylinder FLPIs the proportion of the low pressure cylinder output, TCHIs the main steam admission volume and the time constant of the steam chamber, TRHIs the turbine reheat time constant, TCOIs the cross-tube time constant; the steam enters the cylinder to do work through a valve with a certain size, wherein the steam sequentially enters the high/middle/low pressure cylinder in sequence, so that FHP、FIP、FLPThe sum is 1, which represents that the steam in the three cylinders is the total amount of the steam. The steam of the three cylinders drives the generator to rotate together, TCH、TRH、TCOThree time constants represent the movement of steam between cylinders, the speed of which depends on TCH、TRH、TCOThree time constants.
As shown in fig. 4, the optimal control method of the overspeed protection control optimization system of the pressurized water reactor nuclear power generating unit comprises the following steps:
(1) the trigger signal acquisition module acquires a trigger signal from the speed regulator; the trigger signals comprise power deviation and rotating speed deviation of a power system in which the pressurized water reactor nuclear power unit and the pressurized water reactor nuclear power unit are located and high-frequency generator tripping signals of the pressurized water reactor nuclear power unit;
(2) the logic judgment module judges whether the high-frequency generator tripping signal of the pressurized water reactor nuclear power unit is 1 or not, the high-frequency generator tripping signal is 0 when the pressurized water reactor nuclear power unit normally operates, and if the rotating speed of the pressurized water reactor nuclear power unit rises to reach a threshold value of 110% per unit or the power difference value between the unit and a power grid reaches a threshold value of 30%, the high-frequency generator tripping signal is changed into 1. If the high-frequency cutting machine signal is 1, a valve quick closing instruction is immediately given to a valve closing signal generating module, and the valve closing signal generating module outputs a signal to control a high-pressure valve and a medium-pressure valve of a pressurized water reactor nuclear power unit steam turbine to be quickly closed;
(3) when the logic judgment module judges that the high-frequency cutting machine signal of the pressurized water reactor nuclear power unit is 0, the logic judgment module continuously judges whether the power deviation is greater than or equal to 30% per unit value, if the logic judgment module judges that the power deviation is greater than or equal to 30% per unit value, a valve quick closing instruction is immediately given to a valve closing signal generation module, and the valve closing signal generation module outputs a signal to control a high-pressure valve and a medium-pressure valve of a pressurized water reactor nuclear power unit steam turbine to be closed quickly;
(4) when the logic judgment module judges that the high-frequency generator tripping signal of the pressurized water reactor nuclear power unit is 0 and the power deviation is less than 30 per unit value, the logic judgment module continuously judges whether the rotating speed deviation is more than or equal to 3 per unit value, if the logic judgment module judges that the rotating speed deviation is more than or equal to 3 per unit value, a valve quick closing instruction is immediately given to the valve closing signal generation module, and the valve closing signal generation module outputs a signal to control a high-pressure valve of a pressurized water reactor nuclear power unit steam turbine to be quickly closed;
(5) and when the logic judgment module judges that the high-frequency generator tripping signal of the pressurized water reactor nuclear power unit is 0, the power deviation is less than 30% per unit value and the rotating speed deviation is less than 3% per unit value, the pressurized water reactor nuclear power unit overspeed protection control system quits operation, and the speed regulator plays a role in regulating the rotating speed of the steam turbine again.
The power deviation is the difference between the mechanical power output by the pressurized water reactor nuclear power unit and the electromagnetic power output to the power grid side by the pressurized water reactor nuclear power unit; the rotating speed deviation is the difference between the rotating speed of a steam turbine of the pressurized water reactor nuclear power unit and the rated rotating speed. The high-frequency generator tripping signal is a load shedding signal of the pressurized water reactor nuclear power generator set.
Based on a Power System Analysis Software Package (PSASP), the pressurized water reactor nuclear Power unit model with the pressurized water reactor nuclear Power unit overspeed protection control optimization System is simulated, and simulation data are shown in a table 2:
table 2 simulation data detail table
Simulation parameters Specific numerical value
Simulation step length/s 0.01
Simulation total duration/s 150
The simulation steps are as follows:
(1) the pressurized water reactor nuclear power unit model with the pressurized water reactor nuclear power unit overspeed protection control optimization system is connected into a power grid, the capacity of the power grid is set to be far larger than that of a pressurized water reactor nuclear power unit, for example, the power grid capacity is 26000MW, the capacity of the pressurized water reactor nuclear power unit is 1000MW, load flow calculation is carried out on the power grid, and a steady state value is recorded as an initial value of transient simulation, as shown in Table 3.
Table 3 power network load flow calculation steady state value detail table
Unit parameters Steady state value
Active power/p.u. 0.80
Reactive power/p.u. 0.11
Voltage/p.u. 1.00
Phase angle/° 18.66
(2) The three-phase short-circuit fault occurs at the time of 10.00s when the outlet end of the main transformer of the pressurized water reactor nuclear power unit is arranged, and the fault is recovered at 10.25 s.
(3) Respectively recording a waveform diagram of the rotation speed fly-up of the nuclear power unit of the reactor under the action of the overspeed protection control system, a waveform diagram of the rotation speed fly-up of the nuclear power unit of the reactor under the action of the existing overspeed protection control system and a waveform diagram of the rotation speed fly-up of the nuclear power unit of the reactor under the action of the overspeed protection control optimization system of the nuclear power unit of the reactor, as shown in fig. 5, 6 and 7:
according to fig. 5, it can be known that the rotating speed peak value of the pressurized water reactor nuclear power unit under the action of the pressurized water reactor nuclear power unit overspeed protection control optimization system without the control system disclosed by the invention under the fault condition is increased to 1.22 per unit, which belongs to very serious overspeed and causes unit trip protection. According to the graph 6, under the action of the optimized overspeed protection control system, the rotating speed peak value of the pressurized water reactor nuclear power unit under the fault condition flies to 1.16 per unit, and according to the graph 7, under the action of the optimized overspeed protection control system of the pressurized water reactor nuclear power unit, the rotating speed peak value of the pressurized water reactor nuclear power unit under the fault condition is limited to 1.06 per unit, so that the effectiveness of the optimized control of the optimized overspeed protection control system of the pressurized water reactor nuclear power unit is verified.
The present invention is not limited to the above embodiments, which are merely preferred embodiments of the present invention, and the present invention is not limited thereto, and any modifications, equivalents and improvements made within the spirit and principle of the present invention should be included in the protection scope of the present invention.

Claims (4)

1. The optimization control method of the pressurized water reactor nuclear power unit overspeed protection control optimization system is characterized by comprising the following steps of: the method comprises the following steps:
(1) the trigger signal acquisition module acquires a trigger signal from the speed regulator; the trigger signals comprise power deviation and rotating speed deviation of a power system in which the pressurized water reactor nuclear power unit and the pressurized water reactor nuclear power unit are located and high-frequency generator tripping signals of the pressurized water reactor nuclear power unit;
(2) the logic judgment module judges whether a high-frequency cutting machine signal of the pressurized water reactor nuclear power unit is 1, if so, a valve quick closing instruction is immediately given to the valve closing signal generation module, and the valve closing signal generation module outputs a signal to control quick closing of a high-pressure valve and a medium-pressure valve of a pressurized water reactor nuclear power unit steam turbine;
(3) when the logic judgment module judges that the high-frequency cutting machine signal of the pressurized water reactor nuclear power unit is 0, the logic judgment module continuously judges whether the power deviation is greater than or equal to a set value, if the logic judgment module judges that the power deviation is greater than or equal to the set value, a valve quick-closing instruction is immediately given to a valve closing signal generation module, and the valve closing signal generation module outputs a signal to control a high-pressure valve and a medium-pressure valve of a pressurized water reactor nuclear power unit steam turbine to be quickly closed;
(4) when the logic judgment module judges that the high-frequency cutting machine signal of the pressurized water reactor nuclear power unit is 0 and the power deviation is smaller than a set value, the logic judgment module continuously judges whether the rotating speed deviation is larger than or equal to the set value or not, if the logic judgment module judges that the rotating speed deviation is larger than or equal to the set value, a valve quick closing instruction is immediately given to a valve closing signal generation module, and the valve closing signal generation module outputs a signal to control a high-pressure valve of a turbine of the pressurized water reactor nuclear power unit to be quickly closed;
(5) when the logic judgment module judges that the high-frequency generator tripping signal of the pressurized water reactor nuclear power unit is 0, the power deviation is smaller than a set value and the rotating speed deviation is smaller than the set value, the pressurized water reactor nuclear power unit overspeed protection control system quits operation, and the speed regulator plays a role in regulating the rotating speed of the steam turbine again;
the system comprises a trigger signal acquisition module, a logic judgment module and a valve closing signal generation module, wherein the trigger signal acquisition module is connected with a speed regulator and a power grid side of the nuclear power unit and used for acquiring a trigger signal; the trigger signals comprise power deviation and rotating speed deviation of a power system in which the pressurized water reactor nuclear power unit and the pressurized water reactor nuclear power unit are located and high-frequency generator tripping signals of the pressurized water reactor nuclear power unit; the logic judgment module is respectively connected with the trigger signal acquisition module and the valve closing signal generation module and is used for judging according to the trigger signal acquired by the trigger signal acquisition module and giving a valve quick closing instruction to the valve closing signal generation module; the steam valve closing signal generating module is connected with a steam turbine of the nuclear power unit and used for receiving a steam valve quick closing instruction of the logic judging module and outputting a signal to control quick closing of a high-pressure steam valve and a medium-pressure steam valve of the steam turbine of the pressurized water reactor nuclear power unit.
2. The optimized control method of the overspeed protection control optimization system of the pressurized water reactor nuclear power unit according to claim 1, characterized by comprising the following steps: the power deviation is the difference between the mechanical power output by the pressurized water reactor nuclear power generator set and the electromagnetic power output to the power grid side by the pressurized water reactor nuclear power generator set; the rotating speed deviation is the difference between the rotating speed of a steam turbine of the pressurized water reactor nuclear power unit and the rated rotating speed.
3. The optimized control method of the overspeed protection control optimization system of the pressurized water reactor nuclear power unit according to claim 1 or 2, characterized by comprising the following steps: the set value of the power deviation is a 30% per unit value.
4. The optimized control method of the overspeed protection control optimization system of the pressurized water reactor nuclear power unit according to claim 1 or 2, characterized by comprising the following steps: the set value of the rotational speed deviation is a 3% per unit value.
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