A pressurized water reactor nuclear cogeneration control method and system

Abstract

The application provides a pressurized water reactor nuclear cogeneration control method and system, which comprises heat supply steam control, turbine control and reactor power control; the heat supply steam control calculates a heat supply deviation of a rated heat supply extraction steam flow and an actual heat supply extraction steam flow, and adjusts the actual heat supply extraction steam flow by taking the heat supply deviation as a feedback adjustment amount; the turbine control calculates a power deviation of a rated electric power and an actual electric power, and controls the opening degree of a main steam regulating valve to adjust the actual power of the turbine by taking the power deviation as a feedback adjustment amount of the turbine control and combining a heat load deviation; and the reactor power control adjusts the reactor power according to a steam generation end average temperature signal, the heat supply deviation, a pressure signal and a reactor power signal. The application increases the heat supply steam control to control the heat supply steam flow, and increases feedforward adjustment on the basis of the turbine control system and the reactor power control, so that the pressurized water reactor nuclear cogeneration unit can meet the needs of the thermal and electric loads more quickly and better.

Description

TECHNICAL FIELD

[0001] The present application belongs to the field of comprehensive utilization of nuclear energy, and particularly relates to a pressurized water reactor nuclear energy cogeneration control method and system. BACKGROUND

[0002] The statements in this section merely provide background information related to the present application and do not necessarily constitute the prior art.

[0003] As a stable, clean and low-carbon energy, nuclear energy can effectively replace coal as one of the main energy pillars in China in the future, and the non-electric utilization mode of nuclear energy has become one of the mainstream research directions in the academic field.

[0004] The mainstream pressurized water reactor nuclear power plant has a low steam grade, and the main steam is saturated steam, so the thermal-electric conversion efficiency is only about 33%. The nuclear energy cogeneration can make the energy utilization rate reach 80% or even higher.

[0005] The current research on the control system and method of the cogeneration mainly focuses on the thermal power unit, and the research on the domestic pressurized water reactor unit mainly focuses on the system design and configuration optimization, and there is little related research. The nuclear power unit often adopts the mode of reactor following the turbine, and if it is directly used in the cogeneration system, the reactor cannot be adjusted according to the change of the thermal load, and the thermal and electric load demands cannot be met simultaneously due to the thermal-electric coupling. In addition, the nuclear power two-loop system has a steam-water separation reheater, and after the cogeneration, the extraction of steam will cause the decrease of the exhaust pressure of the high-pressure cylinder, thereby affecting the normal work of the low-pressure cylinder. SUMMARY

[0006] In order to overcome the defects of the prior art, the present application provides a pressurized water reactor nuclear energy cogeneration control method and system.

[0007] To achieve the above object, one or more embodiments of the present application provide the following technical solutions:

[0008] The present application provides a pressurized water reactor nuclear energy cogeneration control method, which comprises: heat supply steam control, turbine control and reactor power control.

[0009] The heat supply steam control calculates the heat supply deviation of the rated heat supply extraction steam flow and the actual heat supply extraction steam flow required by the heat network heat exchanger, and adjusts the actual heat supply extraction steam flow by taking the heat supply deviation as the feedback adjustment amount of the heat supply steam control.

[0010] The turbine control calculates the power deviation of the rated electric power and the actual electric power of the turbine, takes the power deviation as the feedback adjustment amount of the turbine control and the heat load deviation signal in the heat supply steam control, and controls the opening degree of the main steam regulating valve to adjust the actual power of the turbine in combination with the heat load deviation signal.

[0011] The reactor power control adjusts the reactor power according to the steam generation end average temperature signal, the heat load deviation signal, the pressure signal in the pipeline after the main steam regulating valve opening degree is adjusted, and the reactor power signal.

[0012] The second aspect of the present application provides a pressurized water reactor cogeneration control system, comprising: a first control channel, a second control channel and a third control channel.

[0013] The first control channel is used for calculating a heat supply deviation of a rated heat supply extraction steam flow and an actual heat supply extraction steam flow required by a heat network heat exchanger, and adjusting the actual heat supply extraction steam flow by taking the heat supply deviation as a feedback adjustment amount of heat supply steam control.

[0014] The second control channel is used for calculating a power deviation of a rated electric power and an actual electric power of a steam turbine and the heat load deviation signal in the first control channel, and controlling the main steam regulating valve opening degree to adjust the actual power of the steam turbine by taking the power deviation as a feedback adjustment amount of steam turbine control and combining the heat load deviation signal.

[0015] The third control channel is used for adjusting the reactor power according to the steam generation end average temperature signal, the heat load deviation signal, the pressure signal in the pipeline after the main steam regulating valve opening degree is adjusted, and the reactor power signal.

[0016] The above one or more technical solutions have the following beneficial effects:

[0017] (1) The present application increases a heat supply steam control subsystem to control the heat supply steam flow, and increases feedforward adjustment on the basis of the steam turbine control subsystem and the reactor power control subsystem, so that the pressurized water reactor cogeneration unit can meet the heat and electric load needs faster and better.

[0018] (2) The present application increases heat supply feedforward in the steam turbine control subsystem, reduces the lag time of the main steam regulating valve action, and makes the main steam regulating valve action more timely.

[0019] (3) The present application increases heat supply feedforward in the reactor power control subsystem, reduces the lag time of the control rod action, and makes the control rod action more timely.

[0020] The advantages of the additional aspects of the present application will be partially given in the following description, partially become obvious from the following description, or be understood through the practice of the present application. BRIEF DESCRIPTION OF DRAWINGS

[0021] The accompanying drawings, which form a part of this specification, are included to provide a further understanding of the application and are incorporated herein by reference. The embodiments depicted herein are provided by way of example only and together with the specification serve to explain the application.

[0022] Figure 1 Flow chart of the pressurized water reactor nuclear cogeneration control method of the first embodiment.

[0023] Figure 2 Structure diagram of the pressurized water reactor nuclear cogeneration control system of the second embodiment. DETAILED DESCRIPTION

[0024] Embodiment one

[0025] As shown in the figure, the embodiment discloses a pressurized water reactor nuclear cogeneration control method, which comprises first heating steam control, second steam turbine control and third reactor power control; Figure 1

[0026] The first heating steam control calculates the rated heating extraction steam flow required by the heating network heat exchanger according to the heating load instruction input by the user, and takes the deviation between the rated heating extraction steam flow and the actual heating extraction steam flow as a first feedback adjustment amount to participate in the heating steam control, so as to adjust the actual heating extraction steam flow.

[0027] Meanwhile, the first feedback adjustment amount is taken as a first feedforward compensation amount of the second steam turbine control and the third reactor power control.

[0028] The second steam turbine control calculates the rated electric power of the steam turbine according to the electric load instruction input by the user, takes the deviation between the rated electric power and the actual electric power as a second feedback adjustment amount, and controls the opening degree of the main steam regulating valve according to the second feedback adjustment amount and the first feedforward compensation amount to adjust the actual power of the steam turbine.

[0029] The pressure signal in the pipeline at the outlet end of the adjusted main steam regulating valve is measured, and the adjusted pressure signal is taken as a second feedforward compensation amount of the third reactor power control.

[0030] The third reactor power control adjusts the reactor power according to the steam end average temperature signal, the first feedforward compensation amount, the second feedforward compensation amount and the reactor power signal.

[0031] Embodiment two

[0032] As shown in the figure, the embodiment discloses a pressurized water reactor nuclear cogeneration control system, which comprises a pressurized water reactor nuclear cogeneration unit and a control system for controlling the pressurized water reactor nuclear cogeneration unit. Figure 2

[0033] ​​The pressurized water reactor combined heat and power unit comprises a steam generator 1, a main steam regulating valve 2, a pressure sensor 3, a steam turbine high-pressure cylinder 4, a steam-water separation reheater 5, a low-pressure cylinder inlet regulating valve 6, a steam turbine low-pressure cylinder 7, a generator 8, a condenser 9, a low-pressure regenerator 10, a deaerator 11, a feed water pump 12, a high-pressure regenerator 13, a heat network heat exchanger 14, a heat supply steam extraction regulating valve 15, a heat network regenerator 16, a main pump 17, a reactor pressure vessel 18 and a control rod drive mechanism 19;

[0034] The control rod drive mechanism 19 is installed on the upper portion of the reactor pressure vessel 18 to adjust the rod position of the control rod; the reactor pressure vessel 18 has a coolant inlet and a coolant outlet, the coolant outlet is connected with the primary side inlet of the steam generator 1 through a pipeline, the primary side outlet of the steam generator 1 is connected with the inlet of the main pump 17 through the heat network regenerator 16, and the outlet of the main pump 17 is connected with the inlet of the reactor pressure vessel 18 through a pipeline.

[0035] The steam inlet of the main steam regulating valve 2 is connected with the top secondary side outlet of the steam generator 1 through a main steam pipeline, the outlet of the main steam regulating valve 2 is connected with the inlet of the steam turbine high-pressure cylinder 4 through a pipeline, and the outlet of the steam turbine high-pressure cylinder 4 is connected with the inlet of the steam-water separation reheater 5 and the deaerator 11 through a three-way pipe; the steam-water separation reheater 5 comprises a steam-water separator and two-stage reheaters, each of the two-stage reheaters comprises a tube side and a shell side, the shell side inlet of the first-stage reheater is connected with the first-stage steam extraction outlet of the high-pressure cylinder 4 through a pipeline to receive the unadjusted steam extraction from the high-pressure cylinder 4, and the second-stage reheater is connected with the main steam pipeline to receive the main steam extraction; the tube side outlet of the second-stage reheater of the steam-water separation reheater 5 is connected with the inlet of the low-pressure cylinder inlet regulating valve 6 through a three-way pipe, and the outlet of the low-pressure cylinder inlet regulating valve 6 is connected with the inlet of the steam turbine low-pressure cylinder 7 through a pipeline.

[0036] The low-pressure regenerator 10, the deaerator 11, the feed water pump 12 and the high-pressure regenerator 13 are arranged between the condenser 9 and the steam generator 1, wherein the feed water inlet of the condenser 9 is connected with the inlet of the low-pressure regenerator 10 through a pipeline; the inlet of the deaerator 11 is connected with the outlet of the low-pressure regenerator 10 through a pipeline; the top of the deaerator 9 is connected with the bottom outlet of the steam-water separator in the steam-water separation reheater 5 through a pipeline; the outlet of the deaerator 11 is connected with the inlet of the high-pressure regenerator 13 through the feed water pump 12; and the outlet of the high-pressure regenerator 13 is connected with the middle secondary side inlet of the steam generator 1 through a valve and a pipeline.

[0037] The heat supply extraction regulating valve 15 is installed on the steam extraction inlet pipe of the heat network heater 14, and is connected to the exhaust port of the high-pressure cylinder 4 through a pipe; the heat network heater 14 takes the exhaust steam of the high-pressure cylinder 4 as a heat source, and controls the heat supply amount by adjusting the opening of the heat supply extraction regulating valve 15; the bottom of the heat network heater 14 is connected to the bottom of the condenser 9 through a pipe; and the drain of the heat network heater 14 is fed into the condenser 9.

[0038] The control system comprises a reactor power control system 21, a steam turbine control system 22, a heat supply steam control system 23, a heat load input instruction 25 and an electric load input instruction 24.

[0039] The pressurized water heap cogeneration unit is connected with the control system, and can be divided into a first control channel, a second control channel and a third control channel.

[0040] The first control channel comprises the heat network heater 14, the heat supply extraction regulating valve 15, the heat supply steam control system 23 and the heat load input instruction 25; the heat supply steam control system 23 takes the actual heat supply amount as a controlled parameter, receives the heat load instruction 25, calculates the heat supply extraction flow required by the heat network heater 14, generates the control amount of the heat supply extraction regulating valve 15, takes the heat supply extraction flow as a controlled parameter, and controls the opening of the heat supply extraction regulating valve 15 by using the feedback adjustment amount to adjust the actual heat supply amount.

[0041] Specifically, the heat supply steam control system 23 is used for adjusting the flow of the heat supply extraction to control the heat supply amount, and generating a control component ΔQ by using the deviation between the set heat load Q0 and the actual heat supply amount Q; the control component ΔQ is used as a feedback signal of the first control unit to participate in the heat supply control, and is used as a feedforward compensation amount of the steam turbine control system and the reactor power control system to participate in the steam turbine power control and the reactor power control; the heat supply steam control system stores a heat supply amount-extraction flow relationship diagram, and can convert the heat load input instruction into the required heat supply extraction flow.

[0042] The second control channel comprises the main steam regulating valve 2, the high-pressure steam turbine 4, the steam-water separation reheater 5, the low-pressure cylinder inlet regulating valve 6, the low-pressure steam turbine 7, the generator 8, the condenser 9, the low-pressure regenerator 10, the deaerator 11, the feed water pump 12, the high-pressure regenerator 13, the steam turbine control system 22 and the electric load input instruction 24; the steam turbine control system takes the actual electric power as a controlled parameter, generates a main steam regulating valve control amount by receiving the electric load input instruction, controls the opening of the main steam regulating valve by using a feedback adjustment amount and a heat supply deviation feedforward compensation amount, and adjusts the actual power.

[0043] Specifically, the steam turbine control system is used to adjust the main steam flow to control the electric power, and stores a main steam regulating valve PID control system inside, which generates a control component △P by the deviation of the set electric power P0 and the actual electric power P measured value, and the component is used as a feedback signal of the second control unit to participate in the steam turbine control, and the regulating stage pressure signal is transmitted to the reactor power control. The signal is used as a feedforward compensation of the reactor power control system to participate in the reactor power control.

[0044] The third control channel includes a steam generator 1, a pressure sensor 3, a cold section temperature sensor 16, a main pump 17, a reactor pressure vessel 18, a control rod drive mechanism 19, a hot section temperature sensor 20 and a reactor power control system 21. The reactor power control system 21 adopts a coolant average temperature program system, receives the temperature signal T1 from the cold section temperature sensor, the temperature signal T2 from the hot section temperature sensor, the pressure signal P1 from the pressure sensor and the heat supply deviation signal △Q from the first control unit, generates a control rod action signal to control the control rod drive mechanism 19, and feeds back the adjustment amount, the electric power deviation feedforward compensation and the heat supply deviation feedforward compensation to coordinate control the control rod drive mechanism 19 to adjust the reactor power.

[0045] Specifically, the reactor power control system 21 is used to adjust the control rod position to control the reactor power, receives the cold section temperature signal T1, the hot section temperature signal T2, the regulating stage pressure signal p, the heat supply deviation signal △Q and the reactor power signal N, and controls the control rod position Bl.

[0046] As a preferred embodiment, the heat supply steam control system 23 includes a first acquisition module, a first processing module and a first control module; the first acquisition module acquires the heat load input instruction Q0 and the actual heat supply extraction steam flow q, converts the heat load input instruction Q0 into the required heat supply extraction steam flow q0 under the heat load, and internally sets a subtracter, and finally outputs the heat supply extraction steam flow deviation signal △q, wherein △q=q0-q; the first processing module receives the heat supply extraction steam flow deviation signal and converts it into a heat supply extraction steam regulating valve opening degree control instruction μ2 through a PID control system; the first control module is electrically connected with the heat supply steam regulating valve, controls the regulating valve opening degree to adjust the heat supply extraction steam flow;

[0047] The steam turbine control system 22 comprises a second acquisition module, a second processing module and a second control module; the second acquisition module can acquire an electric load input instruction P0, an actual steam turbine electric power P and a heat load deviation signal AQ; the heat load deviation signal AQ = Q0-q*Ah, wherein Ah is the enthalpy drop of the heating extraction steam in the heat network heater; the second acquisition module is internally provided with an adder, and outputs an electric load deviation signal AP, AP = P0-P; the second acquisition module takes the heat load deviation signal AQ as a feedforward compensation quantity and takes the electric load deviation signal AP as a feedback compensation quantity; the second acquisition module processes the electric load deviation signal AP and the heat load deviation signal AQ, and outputs a total deviation signal AF; the second processing module receives the total deviation signal AF and outputs a main steam valve opening degree signal m1 through PI control; the second control module is electrically connected with the main steam valve; the second control module receives the main steam valve opening degree signal and adjusts the main steam flow by controlling the main steam valve opening degree, so as to control the actual electric power P of the steam turbine unit.

[0048] The reactor power control system 21 comprises a third acquisition module, a third processing module and a third control module; the third acquisition module is electrically connected with a reactor pressure vessel, a cold section temperature sensor, a hot section temperature sensor and a pressure sensor; the third acquisition module receives a cold section temperature signal, a hot section temperature signal, a pressure signal and a reactor power signal;

[0049] The third acquisition module comprises an average temperature given value channel, an average temperature measurement channel and a power mismatch deviation channel.

[0050] The average temperature given value channel stores a pressure load conversion function and a coolant average temperature given value function, receives a pressure signal p1 of the pressure sensor and converts the load signal through the pressure load conversion function; the pressure load conversion function is wherein a, b, c and d are constants, and Y is the ratio of the current steam turbine power to the rated power; the average temperature given value function converts the load signal into an average temperature to obtain a coolant average temperature given value signal; the average temperature given value function is T ref =k1* e, wherein e and k are constants. The average temperature measurement channel receives a cold section temperature sensor temperature signal T1 and a hot section temperature sensor temperature signal T2 and converts the same into an average temperature measurement value signal T avg ; the T avg =(T 1+ T2) / 2.

[0051] The power mismatch deviation channel receives a reactor power signal N0, a load signal P, and a thermal power deviation signal ΔQ, and converts them into a power mismatch deviation signal; specifically, N0 is subtracted from P by an adder, and the output deviation enters a differential deviation unit and outputs a nonlinear gain K1 after entering a nonlinear gain unit; the load signal P outputs a variable gain K2 after entering a variable gain unit; the nonlinear gain K1 and the variable gain K2 are multiplied by a multiplier to obtain the power mismatch deviation signal.

[0052] The third processing module receives an average temperature measurement signal, a power mismatch deviation signal, and an average temperature setpoint signal, and outputs a control rod direction signal and a rod speed signal Bs after entering a rod speed program unit through an adder; the rod speed program unit is used to adjust the control rod of the rod control system;

[0053] The third control module receives the control rod direction signal and the rod speed signal Bs, and adjusts the reactor power by controlling the action of the control rod;

[0054] The present application adds a heating steam control system to control the heating steam flow, and adds a feedforward regulation on the basis of the steam turbine control system and the reactor power control system, so that the pressurized water reactor nuclear energy cogeneration unit can meet the needs of the thermal power load more quickly and better.

[0055] Those skilled in the art should understand that the above-mentioned modules or steps of the present application can be realized by a general computer device, and alternatively, they can be realized by program codes executable by a computing device, so that they can be stored in a storage device and executed by a computing device, or they can be respectively manufactured into individual integrated circuit modules, or a plurality of modules or steps among them can be manufactured into a single integrated circuit module. The present application is not limited to any specific combination of hardware and software.

[0056] The above describes the specific embodiments of the present application in combination with the accompanying drawings, but is not a limitation on the protection scope of the present application. Those skilled in the art should understand that various modifications or variations made by those skilled in the art on the basis of the technical solutions of the present application without creative labor are still within the protection scope of the present application.

Claims

1. A control method for pressurized water reactor nuclear cogeneration, characterized in that, include: Heating steam control, turbine control, and reactor power control; The heating steam control calculates the heating deviation between the rated heating steam flow rate required by the heat exchanger of the heating network and the actual heating steam flow rate, and uses the heating deviation as the feedback adjustment amount of the heating steam control to adjust the actual heating steam flow rate. The turbine control calculates the power deviation between the rated power and the actual power of the turbine, uses the power deviation as the feedback adjustment amount of the turbine control, and combines it with the heating deviation to control the opening of the main steam regulating valve to adjust the actual power of the turbine. The reactor power control adjusts the reactor power based on the average temperature signal at the steam generator end, the heating deviation, the pressure signal in the pipeline after the main steam regulating valve opening is adjusted, and the reactor power signal. Specifically: The pressure signal is converted into a load signal according to the pressure-load conversion function; The load signal is converted into a coolant average temperature setpoint signal according to the average temperature setpoint function. The power mismatch deviation signal is calculated based on the load signal, reactor power signal, and heating deviation. The control rod position signal is calculated based on the average temperature signal at the steam generator end, the setpoint signal of the average temperature of the coolant, and the power mismatch deviation signal. The control rod is then controlled to adjust the reactor power. The average temperature signal at the steam generating end is calculated based on the cold section temperature signal and the hot section temperature signal of the steam generator.

2. The control method for pressurized water reactor nuclear cogeneration as described in claim 1, characterized in that, The heating steam control system converts the user-input heat load command into the required heating steam flow rate for the heat network heat exchanger based on the heat supply-extraction steam flow rate relationship diagram.

3. A pressurized water reactor nuclear cogeneration control system, used to control a pressurized water reactor cogeneration unit, characterized in that, include: The pressurized water reactor nuclear cogeneration control system is divided into a first control channel, a second control channel, and a third control channel, comprising a reactor power control system (21), a steam turbine control system (22), a heating steam control system (23), a heat load input command (25), and an electrical load input command (24). The first control channel is used to calculate the heating deviation between the rated heating steam flow rate required by the heat exchanger and the actual heating steam flow rate, and to use the heating deviation as a feedback adjustment amount for heating steam control to adjust the actual heating steam flow rate. The second control channel is used to calculate the power deviation between the rated electric power and the actual electric power of the steam turbine, and uses the power deviation as the feedback adjustment amount of the steam turbine control. Combined with the heat supply deviation, the opening of the main steam regulating valve is controlled to adjust the actual power of the steam turbine. The third control channel is used to adjust the reactor power based on the average temperature signal at the steam generator end, the heating deviation, the pressure signal in the pipeline after the main steam regulating valve opening is adjusted, and the reactor power signal. The third control channel includes a steam generator (1), a pressure sensor (3), a cold section temperature sensor (26) of the steam generator, a main pump (17), a reactor pressure vessel (18), a control rod drive mechanism (19), a hot section temperature sensor (20) of the steam generator, and a reactor power control system (21). The reactor power control system includes: a third acquisition module, a third processing module, and a third control module; The third acquisition module is used to convert the pressure signal into a load signal according to the pressure-load conversion function; to convert the load signal into a coolant average temperature setpoint signal according to the average temperature setpoint function; to calculate the power mismatch deviation signal according to the load signal, reactor power signal, and heating deviation; and to calculate the average temperature signal at the steam generator end according to the cold section temperature signal and hot section temperature signal of the steam generator. The third processing module is used to calculate the control rod position signal according to the average temperature signal at the steam generator end, the power mismatch deviation signal, and the coolant average temperature setpoint signal. The third control module is used to control the action of the control rods based on the rod position signal, thereby adjusting the reactor power.

4. A pressurized water reactor nuclear cogeneration control system as described in claim 3, characterized in that, The first control channel includes a heat exchanger (14), a heating extraction steam regulating valve (15), a heating steam control system (23), and a heat load input command (25); the steam inlet of the heat exchanger (14) is connected to the heating extraction steam regulating valve (15). The heating steam control system (23) is used to calculate the rated heating steam flow rate required by the heat network heat exchanger (14) according to the heat load command (25) input by the user, and use the heating deviation between the rated heating steam flow rate and the actual heating steam flow rate as feedback adjustment amount to control the opening of the heating steam extraction regulating valve (15) to adjust the actual heating steam flow rate. The second control channel includes a steam generator (1), a main steam regulating valve (2), a high-pressure cylinder of the steam turbine (4), a steam turbine control system (22), and an electrical load input command (24). The steam inlet of the main steam regulating valve (2) is connected to the secondary side outlet at the top of the steam generator (1) through a main steam pipeline, and the outlet of the main steam regulating valve (2) is connected to the inlet of the high-pressure cylinder (4) of the steam turbine through a pipeline. The turbine control system (22) is used to calculate the rated power of the turbine according to the electrical load command (24) input by the user, calculate the heating deviation according to the heat load input command in the first control channel and the enthalpy drop of the heating extraction steam flow rate, and use the power deviation between the rated power and the actual power as the feedback adjustment amount, and control the opening of the main steam regulating valve (2) in combination with the heating deviation to adjust the actual power of the turbine. The pressure signal in the steam inlet pipe of the high-pressure cylinder (4) of the steam turbine after adjustment is measured, and the adjusted pressure signal is used as the feedforward compensation amount of the third control channel. The pressure sensor (3) is installed on the pipe at the outlet of the main steam regulating valve (2) to measure the pressure signal in the pipe; the hot section temperature sensor (20) of the steam generator is installed on the pipe at the outlet of the reactor pressure vessel (18); The reactor power control system (21) is used to control the operation of the control rod drive mechanism (19) based on the average temperature signal at the steam generation end, the heating deviation, the pressure signal measured by the pressure sensor (3) and the reactor power signal, so as to adjust the reactor power.

5. A pressurized water reactor nuclear cogeneration control system as described in claim 4, characterized in that, The heating steam control system includes a first acquisition module, a first processing module, and a first control module; The first acquisition module has a built-in adder, which is used to calculate the heating deviation based on the acquired heat load command and the actual heating steam extraction flow rate; The first processing module is used to calculate the valve opening command based on the heating deviation; The first control module is used to control the opening of the heating extraction steam regulating valve (15) according to the valve opening command to regulate the heating extraction steam flow.

6. A pressurized water reactor nuclear cogeneration control system as described in claim 4, characterized in that, The steam turbine control system includes a second acquisition module, a second processing module, and a second control module; The second acquisition module has a built-in adder, which is used to calculate the power deviation based on the acquired electrical load input command and the actual steam turbine power, and to calculate the heating deviation based on the heat load command and the enthalpy drop of the heating extraction steam flow rate. The second processing module calculates the total deviation signal using the heating deviation as the feedforward compensation amount and the power deviation as the feedback compensation amount; and calculates the valve opening signal of the main steam regulating valve (2) based on the total deviation signal. The second control module controls the main steam regulating valve (2) according to the valve opening signal to adjust the main steam flow and thus control the actual power of the turbine unit.

7. A pressurized water reactor nuclear cogeneration control system as described in claim 3, characterized in that, The third processing module includes: The average temperature signal calculation module at the steam generating end is used to calculate the average temperature signal at the steam generating end based on the cold section temperature signal and the hot section temperature signal of the steam generator. The load signal calculation module is used to convert pressure signals into load signals according to the pressure-load conversion function. The coolant average temperature setpoint signal calculation module is used to convert the load signal into a coolant average temperature setpoint signal according to the average temperature setpoint function. The power mismatch deviation signal calculation module is used to calculate the power mismatch deviation signal based on the load signal, reactor power signal, and heating deviation.

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