Control system and method for heat supply device for nuclear power plant

Abstract

The control system for a heat supply device for a nuclear power plant according to the present invention comprises a first stage pressure measuring device for measuring the first stage pressure of a steam turbine to obtain a first stage pressure signal, a high pressure discharge pressure measuring device for measuring the exhaust pressure of a high pressure cylinder of the steam turbine to obtain an exhaust pressure signal, an extraction heat supply flow measuring device for measuring the extraction heat supply flow rate to obtain an extraction heat supply flow rate signal, a data collection module for collecting the first stage pressure signal, exhaust pressure signal, and extraction heat supply flow rate signals obtained by measurement and transmitting the collected first stage pressure signal, exhaust pressure signal, and extraction heat supply flow rate signals to a core calculation processing module, a core calculation processing module, and a signal output module.

Description

CROSS-REFERENCE TO RELATED APPLICATIONS

[0001] This application claims priority to a Chinese patent application having application number 202210169686.1, filed on February 24, 2022, the entire contents of which are incorporated herein by reference. [Technical field]

[0002] The present invention relates to the technical field of nuclear heat supply, and in particular to a control system and a control method for a heat supply device for a nuclear power plant. [Background technology]

[0003] In our country (China), cities have adopted centralized heat supply systems and mainly use fossil energy for heating, making it difficult to avoid the impact on the environment caused by carbon dioxide emissions. Nuclear energy is a clean, efficient and stable energy source that can provide users with an uninterrupted supply of heat, so nuclear heat supply has become another form of energy supply besides nuclear energy.

[0004] At present, the heat supply system of a nuclear power plant realizes the adjustment of the extraction heat supply parameters by a manual operation method. The change of the extraction amount is related to the synchronous adjustment of the discharge pressure of the high pressure cylinder of the steam turbine (hereinafter referred to as the high pressure discharge pressure) and the electrical load. The stability of the high pressure discharge pressure is directly related to the operating safety of the steam turbine, and the electrical load directly affects the power generation effect of the nuclear power plant. Therefore, it is very important that the adjustment of the extraction heat supply amount meets the requirements. When the extraction volume is performed manually, when the heat supply load fluctuates, multiple parameters, including the extraction volume, high-pressure discharge pressure, and electrical load, need to be synchronously monitored and adjusted, which increases the operational burden on the operator and the probability of manual operation errors. In addition, the suitability of each parameter needs to be checked before manual operation. There is a large operation time delay in adjusting the heat and power load, and the system response speed is slow, which causes a loss of some power generation and presents a potential risk to the safe and stable operation of the unit. In addition, in the normal operation mode (non-heat supply season) of the heat supply unit of a nuclear power plant, the steam turbine operates in a non-extraction heat supply operation state, and the coordinated operation of the reactor and the steam turbine load (hereinafter referred to as reactor-turbine coordination) is generally realized by the reactor power control system automatically tracking the first stage pressure of the steam turbine (representing the load of the steam turbine), and the tracking is based on the function curve of the steam turbine load and the first stage pressure. When extraction heat supply is performed, the correspondence curve between the load of the steam turbine and the initial stage pressure shifts depending on the difference in the amount of extraction heat supply. If the function curve of the steam turbine load and first stage pressure in the original non-bleed heat supply operating condition is maintained, a load matching error will occur due to the coordinated operation of the reactor and turbine. The larger the amount of extraction, the larger the error will be, which will affect the stability of the operating parameters of the reactor system (primary circuit) and potentially have a negative impact on the safe and stable operation of the entire nuclear power unit. Summary of the Invention

[0005] A control system for a nuclear power plant heat supply device according to an embodiment of the first aspect of the present invention includes: a first stage pressure measuring device for measuring a first stage pressure of the steam turbine to obtain a first stage pressure signal; a high pressure discharge pressure measuring device for measuring an exhaust pressure of a high pressure cylinder of the steam turbine to obtain an exhaust pressure signal; a bleed air heat supply flow measurement device for measuring the bleed air heat supply flow rate to obtain a bleed air heat supply flow rate signal; a data collection module for collecting the first stage pressure signal, the exhaust pressure signal, and the bleed heat supply flow rate signal obtained by measurement, and transmitting the collected first stage pressure signal, the exhaust pressure signal, and the bleed heat supply flow rate signal to a core calculation processing module; a core calculation processing module for receiving the initial stage pressure signal, the exhaust pressure signal, and the extraction heat supply flow rate signal transmitted from the data collection module, generating an operation command for each valve in the heat supply device based on the initial stage pressure signal, the exhaust pressure signal, and the extraction heat supply flow rate signal, or determining a load value of the steam turbine using the received signals, and transmitting the operation command or the load value of the steam turbine to a signal output module; and a signal output module for receiving the operation commands or steam turbine load values ​​from the core processing module and transmitting the operation commands or steam turbine load values, respectively, to each associated control system and equipment.

[0006] A method for controlling a heat supply device for a nuclear power plant according to an embodiment of the second aspect of the present invention includes the steps of: Obtaining a first stage pressure signal of the steam turbine, an exhaust pressure signal of a high pressure cylinder of the steam turbine, and an extraction heat supply flow rate signal obtained by measurement, as well as an extraction heat supply flow rate set value and a high pressure discharge pressure set value corresponding to a load demand of the heat supply network; determining a deviation between the extraction heat supply flow rate signal and the extraction heat supply flow rate set value using the extraction heat supply flow rate set value and the extraction heat supply flow rate signal, and determining a deviation between the exhaust pressure signal and the high pressure discharge pressure set value using the high pressure discharge pressure set value and an exhaust pressure signal of a high pressure cylinder of the steam turbine; and controlling the extraction fast closing control valve, the intake control valve of the low pressure cylinder of the steam turbine, and the intake control valve of the high pressure cylinder of the steam turbine based on the deviation and the extraction heat supply flow rate signal, thereby achieving the purpose of regulating the extraction heat supply flow rate, the exhaust pressure of the high pressure cylinder, and the electrical load of the steam turbine unit.

[0007] Another method for controlling a heat supply apparatus for a nuclear power plant according to an embodiment of the third aspect of the present invention includes the steps of: collecting the first stage pressure signal and the extraction heat supply flow rate signal using a data collection module, and performing pre-processing on the collected first stage pressure signal and the extracted heat supply flow rate signal; determining a load value of the steam turbine by selecting a load curve that matches the extraction heat supply flow rate based on the pre-processed first stage pressure signal and the extraction heat supply flow rate signal; and adjusting reactor power by a reactor power control system based on the load value of the steam turbine.

[0008] Additional aspects and advantages of the present invention will be set forth in part in the description which follows, and in part will be apparent from the description, or may be learned by practice of the present disclosure. [Brief description of the drawings]

[0009] The aspects and advantages of the present invention will become more clearly understood from the following detailed description of the embodiments taken in conjunction with the drawings, in which: [Figure 1] 1 is a structural diagram of a control system for a heat supply device for a nuclear power plant according to an embodiment of the present invention; [Diagram 2] 1 is a structural diagram of a control system for a heat supply device for a nuclear power plant according to an embodiment of the present invention; [Diagram 3] FIG. 2 is a first structural diagram of a core processing module in a control system for a heat supply device for a nuclear power plant according to an embodiment of the present invention; [Figure 4] FIG. 2 is a second structural diagram of a core processing module in a control system for a heat supply device for a nuclear power plant according to an embodiment of the present invention. [Diagram 5] FIG. 3 is a third structural diagram of a core processing module in a control system for a heat supply device for a nuclear power plant according to an embodiment of the present invention. [Figure 6] FIG. 4 is a fourth structural diagram of a core calculation module in a control system for a heat supply device for a nuclear power plant according to one embodiment of the present invention. [Figure 7]FIG. 5 is a fifth structural diagram of a core processing module in a control system for a heat supply device for a nuclear power plant according to an embodiment of the present invention. [Figure 8] FIG. 6 is a sixth structural diagram of a core calculation processing module in a control system for a heat supply device for a nuclear power plant according to an embodiment of the present invention. [Figure 9] FIG. 7 is a seventh structural diagram of the core processing module in the control system for the heat supply device for a nuclear power plant according to an embodiment of the present invention. [Figure 10] 1 is a specific application structure diagram of a control system for a heat supply device for a nuclear power plant according to an embodiment of the present invention; [Figure 11] FIG. 2 is a detailed functional block diagram in which a core arithmetic processing module in a control system for a nuclear power plant heat supply device according to one embodiment of the present invention generates operation commands for each valve in the heat supply device. [Figure 12] FIG. 2 is a detailed functional block diagram of a core processing module in a control system for a nuclear power plant heat supply device according to an embodiment of the present invention for determining a load value of a steam turbine; [Figure 13] FIG. 1 is a curve diagram showing the relationship between the first stage pressure and the steam turbine load corresponding to a non-extraction heat supply operating state in a reactor-turbine cooperative control system of an extraction heat supply unit of a nuclear power plant according to one embodiment of the present invention. [Figure 14] FIG. 1 is a curve showing the relationship between the first stage pressure and the steam turbine load corresponding to an operating condition of 500 t / h in a furnace-turbine cooperative control system of an extraction heat supply unit of a nuclear power plant according to one embodiment of the present invention. [Figure 15] FIG. 1 is a curve showing the relationship between the first stage pressure and the steam turbine load corresponding to an operating condition of 1000 t / h in a furnace-turbine cooperative control system of an extraction heat supply unit of a nuclear power plant according to one embodiment of the present invention. [Figure 16] 4 is a flowchart showing a method for generating operation commands for each valve in a control method for a heat supply device for a nuclear power plant according to an embodiment of the present invention. [Figure 17]2 is a flow chart for determining a load value of a steam turbine in a control method for a heat supply device for a nuclear power plant according to an embodiment of the present invention. DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS

[0010] DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS Hereinafter, the embodiments of the present invention will be described in detail, and the embodiments are illustrated in the drawings, in which the same or similar reference numerals indicate elements having the same or similar elements or functions. The embodiments described below with reference to the attached drawings are intended to illustrate the invention without limiting it.

[0011] The present invention provides a control system and method for a heat supply device for a nuclear power plant, the system comprising an initial stage pressure measuring device 1, a high pressure discharge pressure measuring device 2, an extraction heat supply flow rate measuring device 3, a data collection module 4, a core calculation processing module 5, a signal output module 6 and a man-machine interface processing module 7, and using the above devices and modules, generates operation commands for an extraction fast closing control valve (FCV) 12, an intake control valve (GV) 10 of a high pressure cylinder of a steam turbine and an intake control valve (ICV) 11 of a low pressure cylinder of a steam turbine, or determines a load value of the steam turbine, and then controls field equipment based on the operation commands or the load value of the steam turbine. The present invention optimizes and improves the control method of the manual heat supply device, realizes smart adjustment of the system equipment related to the extraction heat supply, increases the degree of automation of the system, and reduces errors caused by human factors. In addition, by bumplessly switching between multiple operation control curves, it is possible to avoid disturbances to the primary circuit parameters caused by changes in the load of the steam turbine during the heat supply operation period, and improve the operating safety and reliability of the nuclear power unit during the heat supply period.

[0012] DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS Hereinafter, a control system and method for a heat supply unit for a nuclear power plant according to an embodiment of the present invention will be described with reference to the drawings. Example 1

[0013] FIG. 1 is a structural diagram of a control system for a nuclear power plant heat supply device according to an embodiment of the present invention. The control system includes a first stage pressure measuring device 1, a high pressure discharge pressure measuring device 2, an extraction heat supply flow rate measuring device 3, a data collection module 4, a core calculation processing module 5 and a signal output module 6. The first stage pressure measuring device 1 is for measuring a first stage pressure of a steam turbine to obtain a first stage pressure signal, The high-pressure discharge pressure measuring device 2 is for measuring the exhaust pressure of a high-pressure cylinder of a steam turbine to obtain an exhaust pressure signal, The extraction heat supply flow rate measuring device 3 is for measuring the extraction heat supply flow rate to obtain an extraction heat supply flow rate signal, the data collection module 4 is for collecting the first stage pressure signal, the exhaust pressure signal, and the bleed heat supply flow rate signal obtained by measurement, and transmitting the collected first stage pressure signal, the exhaust pressure signal, and the bleed heat supply flow rate signal to the core calculation processing module 5; The core calculation processing module 5 receives the first stage pressure signal, the exhaust pressure signal, and the extraction heat supply flow rate signal from the data collection module 4, and generates an operation command for each valve in the heat supply device based on the first stage pressure signal, the exhaust pressure signal, and the extraction heat supply flow rate signal, or determines a load value of the steam turbine using the received signals, and transmits the operation command or the load value of the steam turbine to the signal output module 6; The signal output module 6 is for receiving the operation command or the load value of the steam turbine from the core arithmetic processing module 5, and for transmitting the operation command or the load value of the steam turbine to a field device for control.

[0014] As shown in FIG. 2, the control system for a nuclear power plant heat supply device according to the embodiment of the present invention further includes a man-machine interface processing module 7 for exchanging information with the core arithmetic processing module 5. The information exchange includes manual operation commands in the core computing process, setting value input, signal indication, alarm handling and function switching.

[0015] In addition, before generating an operation command for each valve in the heat supply device based on the first stage pressure signal, the exhaust pressure signal, and the extraction heat supply flow rate signal, or before determining a load value of the steam turbine using the received signals, performing pre-processing on the received first stage pressure signal, exhaust pressure signal, and extraction heat supply flow rate signal; Here, this pre-processing includes performing two-out-of-three redundancy processing on the initial stage pressure signal, the exhaust pressure signal, and the extraction heat supply flow rate signal collected by multiple channels, determining whether a measurement range corresponding to the collected signals exceeds a preset measurement range and whether a value of the collected signals is greater than a preset signal threshold, and sending an alarm signal to the man-machine interface processing module 7 if the measurement range corresponding to the collected signals exceeds the preset measurement range or if the value of the collected signals is greater than the preset signal threshold.

[0016] As shown in FIG. 3, the core processing module 5 in the embodiment of the present invention includes an extraction air flow rate setting value generation module 501, a heat supply flow rate automatic adjustment module 502, and a manual / automatic module 503. The extraction flow rate setting value generation module 501 is for transmitting a flow rate setting value preset according to the load demand of the heat supply network or a setting value provided by an operator through a man-machine interface module to the heat supply flow rate automatic adjustment module 502; The heat supply flow rate automatic adjustment module 502 receives a set value transmitted from the extraction flow rate set value generation module 501, determines a deviation between the extraction heat supply flow rate obtained by measurement and the set value, performs a PID (proportional / integral / differential) calculation based on the deviation, and transmits the calculation result to a manual / automatic module 503; The manual / automatic module 503 receives the calculation result sent from the heat supply flow rate automatic adjustment module 502, and controls the extraction fast closing control valve (FCV) 12 in the heat supply device based on the calculation result.

[0017] As shown in FIG. 4, the core processing module 5 in the embodiment of the present invention further includes a high-pressure discharge pressure setting value generation module 505 and a high-pressure discharge pressure adjustment module 510. The high-pressure discharge pressure setting value generation module 505 is for transmitting a high-pressure discharge pressure setting value preset according to the load demand of the heat supply network or a setting value provided by an operator through the man-machine interface module to the high-pressure discharge pressure adjustment module 510; The high pressure discharge pressure adjustment module 510 receives the exhaust pressure of the high pressure cylinder of the steam turbine obtained by measurement and the exhaust pressure set value transmitted from the high pressure discharge pressure set value generation module 505, determines the deviation between the exhaust pressure obtained by measurement and the set value, performs a PID calculation based on the deviation to obtain a calculation result, and controls the intake control valve (ICV) 11 of the low pressure cylinder of the steam turbine based on the calculation result.

[0018] As shown in FIG. 5 , the core processing module 5 in the embodiment of the present invention further includes a first pressure ratio low pass threshold module 506, a second pressure ratio low pass threshold module 507, an override function trigger condition module 508, an override processing module 509 and an override control module 504; The first pressure ratio low pass threshold module 506 compares the ratio between the exhaust pressure of the high pressure cylinder of the steam turbine obtained by measurement and the first stage pressure signal obtained by measurement with a preset first pressure ratio threshold, and when the ratio between the exhaust pressure of the high pressure cylinder of the steam turbine obtained by measurement and the first stage pressure signal obtained by measurement is greater than the preset first pressure ratio threshold, transmits a signal to close the extraction fast closing control valve (FCV) 12 to the heat supply flow rate automatic adjustment module 502 to realize slow closing of the extraction fast closing control valve (FCV) 12; The second pressure ratio low-pass threshold module 507 compares the ratio between the exhaust pressure of the high pressure cylinder of the steam turbine obtained by measurement and the first stage pressure signal obtained by measurement with a preset second pressure ratio threshold, and sends a signal to close the extraction fast closing control valve (FCV) 12 to an override processing module 509 when the ratio between the exhaust pressure of the high pressure cylinder of the steam turbine obtained by measurement and the first stage pressure signal obtained by measurement is greater than the preset second pressure ratio threshold, to realize rapid closing of the extraction fast closing control valve (FCV) 12. The override processing module 509 is for sending a control command to the override control module 504 when receiving a signal sent from the override function trigger condition module 508, where the override function trigger condition includes heat supply withdrawal (the process in which the extraction volume of the heat supply unit drops from a fixed extraction volume to zero), turbine trip, and OPC operation. In addition, the override control module 504 is provided at the input end of the bleed fast closing control valve (FCV) 12, and is for receiving a control command sent from the override processing module 509, and controlling the quick closing of the bleed fast closing control valve (FCV) 12 based on the control command.

[0019] It should be noted that the first pressure ratio low pass threshold module 506 and the second pressure ratio low pass threshold module 507 have different set values, the latter being lower than the former, and the damage is more serious. After sending a closure signal to the heat supply flow automatic adjustment module 502, if the slow closing operation of the bleed fast closing control valve (FCV) 12 does not prevent the pressure ratio from continuing to decrease, the first pressure ratio low pass threshold module 506 continues to trigger the second pressure ratio low pass threshold module 507, and the override processing module 509 and the override control module 504 protect the bleed fast closing control valve (FCV) 12 from being quickly closed. It should be noted that when the second pressure ratio low pass threshold module 507 is activated, the first pressure ratio low pass threshold module 506 also remains activated until the pressure ratio value is greater than the set value of the threshold module itself.

[0020] As shown in FIG. 6, the core processing module 5 in the embodiment of the present invention further includes a feedforward module 511 . This feedforward module 511 is intended to react in advance to changes in the measured extraction heat supply flow rate to speed up the response of the intake control valve (ICV) 11 of the low pressure cylinder of the steam turbine.

[0021] As shown in FIG. 7, the core processing module 5 in the embodiment of the present invention further includes a heat supply flow load compensation algorithm module 512 . And the heat supply flow rate load compensation algorithm module 512 is for calculating and generating an electrical load control command, and for realizing the automatic increase or decrease of the electrical load of the unit while adjusting the heat supply amount when the total load of the steam turbine is kept unchanged; Here, the heat supply flow load compensation algorithm module 512 outputs an increase / decrease command for the electrical load, which is sent to the steam turbine controller 8 via the signal output module 6 to operate the intake control valve (GV) 10 of the high pressure cylinder of the steam turbine, thereby realizing the adjustment of the electrical load of the unit.

[0022] As shown in FIG. 8 , in this embodiment of the present invention, the core calculation processing module 5 further includes a first curve module 513, a second curve module 514, a third curve module 515, a first switching module 516 and a second switching module 517. A load curve 1 obtained in advance is set in the first curve module 513, and the first curve module 513 is for determining a load value of the steam turbine corresponding to the first stage pressure obtained by measurement based on the load curve 1. The second curve module 514 is set with a load curve 2 obtained in advance, and the second curve module 514 is for determining a load value of the steam turbine corresponding to the first stage pressure obtained by measurement based on the load curve 2; The third curve module 515 is set with a load curve 3 obtained in advance, and the third curve module 515 is for determining a load value of the steam turbine corresponding to the first stage pressure obtained by measurement based on the load curve 3; The first switching module 516 is for receiving a switching signal and switching between the pre-obtained load curve 1 and the pre-obtained load curve 2; The second switching module 517 is for receiving a switching signal to perform switching between the pre-obtained load curve 2 and the pre-obtained load curve 3 . Here, the number of the load curves is determined according to the type of operation status of the extraction heat supply flow rate, and the previously obtained curves 1, 2 and 3 are all created with the reactor power as the abscissa and the first stage pressure as the ordinate.

[0023] In addition, the first switching module 516 and the second switching module 517 are further used to realize the mutual automatic tracking of the load curves before and after switching; the number of flow threshold modules corresponds to the number of switching modules; Here, the number of flow rate threshold modules is determined according to the type of operating condition of the extraction heat supply flow rate.

[0024] As shown in FIG. 9, the core computing module 5 in the embodiment of the present invention further includes a first flow rate threshold module 518, a second flow rate threshold module 519 and a heat supply on / off command processing module 520; the first flow rate threshold module 518 is for comparing the magnitude of the measured bleed air heat supply flow rate with a preset threshold in the first flow rate threshold module 518, and when the measured bleed air heat supply flow rate is greater than the preset threshold, sending a command to the first switching module 516 to switch from load curve 1 to load curve 2; the second flow rate threshold module 519 is for comparing the magnitude of the measured bleed air heat supply flow rate with a preset threshold in the second flow rate threshold module 519, and when the measured bleed air heat supply flow rate is greater than the preset threshold, sending a command to the second switching module 517 to switch from load curve 2 to load curve 3; The heat supply on / off command processing module 520 is for determining whether the heat supply device satisfies the heat supply on condition in response to a heat supply on / off command from an operator, and for transmitting a heat supply on command if the condition is satisfied.

[0025] In short, the control system according to the embodiment of the present invention optimizes and improves the control method of the manual heat supply device, realizes smart adjustment of the system equipment related to the extraction heat supply, and increases the degree of automation. In addition, by bumplessly switching between multiple operation control curves, disturbances to the primary circuit parameters of the reactor during the heat supply operation period can be avoided, and the operation safety and reliability of the nuclear power unit during the heat supply period can be improved. Example 2

[0026] Based on the control system of the above embodiment 1, this embodiment shows a control process for the extraction fast closing control valve (FCV) 12 in the heat supply system, the intake control valve (GV) 10 of the high pressure cylinder of the steam turbine, and the intake control valve (ICV) 11 of the low pressure cylinder of the steam turbine. As shown in FIG. 10, the control process includes first measuring the first stage pressure of the steam turbine with the first stage pressure measuring device 1, measuring the exhaust pressure of the high pressure cylinder of the steam turbine with the high pressure discharge pressure measuring device 2, measuring the extraction heat supply flow rate with the extraction heat supply flow rate measuring device 3, collecting data obtained by the measurements using the data collection module 4 and transmitting the data to the core calculation processing module 5, and then the core calculation processing module 5 receiving the signal transmitted from the data collection module 4, and using the received signal, generating operation commands for the extraction fast closing control valve (FCV) 12, the intake control valve (GV) 10 of the high pressure cylinder of the steam turbine, and the intake control valve (ICV) 11 of the low pressure cylinder of the steam turbine, transmitting the operation commands to the signal output module 6, and the signal output module 6 transmitting the operation command for the extraction fast closing control valve (FCV) 12 to the extraction fast closing control valve (FCV) 12 to control the valves. The control process includes the man-machine interface processing module 7 receiving and displaying information in the process of generating the processed signal and the operation command sent from the core arithmetic processing module 5, the signal output module 6 receiving the operation command sent from the core arithmetic processing module 5, and sending the operation command to the steam turbine controller 8 to control the automatic increase and decrease of the electric load, thereby realizing the thermal-electric coupling, or using the received signal to determine the load value of the steam turbine, and sending the load value of the steam turbine to the signal output module 6, the signal output module 6 sending the signal to the reactor power control system 14, and the reactor power control system 14 controlling the thermal output of the reactor 15 based on the received signal, and then the primary circuit coolant of the reactor 15 is cooled to the reactor system (Nuclear The steam turbine is heated by a steam generator (9) for generating steam, and the main steam passes through a GV (Ground Control Valve) 10 of the high pressure cylinder of the steam turbine and enters the high pressure cylinder of the steam turbine, and then passes through an ICV (Intake Control Valve) 11 of the low pressure cylinder of the steam turbine and enters the low pressure cylinder of the steam turbine. The generator is driven by the operation of the high and low pressure cylinders to generate electricity. Part of the exhaust gas from the high pressure cylinder passes through an extraction duct and an extraction fast closing control valve 12 and directly enters a heat supply network heater 13, which heats the heat supply circulating water that has entered therein, and finally heats the circulating water to realize heat supply to the outside.

[0027] In an embodiment of the present invention, the core processing module 5 receives signals transmitted from the data collection module 4 and uses the signals to generate operation commands for the extraction fast closing control valve (FCV) 12, the intake control valve (GV) 10 of the high pressure cylinder of the steam turbine, and the intake control valve (ICV) 11 of the low pressure cylinder of the steam turbine. FIG. 11 is a detailed internal functional block diagram of core processing module 5, illustrating the detailed relationships between module 5 and modules 4, 6, and 7. Referring to FIG. 11, the module 5 is responsible for important calculation processing tasks. Specifically, the extraction air flow rate set value generation module 501 inputs a flow rate set value that is preset in accordance with the load demand of the heat supply network heater 13 or a flow rate set value provided by the operator via the man-machine interface module 7 to the extraction air flow rate set value generation module 501. Thereafter, the extraction air flow rate set value generation module 501 transmits the flow rate set value to the heat supply flow rate automatic adjustment module 502, and inputs the extraction air heat supply flow rate signal from the data collection module 4 to the heat supply flow rate automatic adjustment module 502. The heat supply flow rate automatic adjustment module 502 compares the deviation between the actual heat supply flow rate and the set value input from 501, performs PID (proportional / integral / differential) calculation based on the deviation, and controls the opening and closing of the valve as an operation command for the FCV valve to adjust the heat supply steam flow rate. Here, the FCV valve position command must pass through a manual / automatic module 503 and an override control module 504 during transmission. The manual / automatic module 503 realizes the manual / automatic switching function of the adjustment circuit. In the automatic mode, the device outputs a command for the automatic adjustment module 502. In the manual mode, the operator sets the valve position of the FCV via a man-machine interface, thereby realizing manual control of the valve.

[0028] Further, as shown in FIG. 11 , when the override processing module 509 receives a signal sent from the override function trigger condition module 508, the override processing module 509 sends a control command to the override control module 504, the override control module 504 receives the control command sent from the override processing module 509 and sends the received control command to the signal output module 6, the signal output module 6 receives the control command and sends the control command to the bleed fast closing control valve (FCV) 12 to control the bleed fast closing control valve (FCV) 12. Here, the override function trigger conditions include heat supply withdrawal, turbine trip, and OPC operation.

[0029] Also, as shown in FIG. 11, the module 505 is used to determine a high pressure discharge pressure set value, and the high pressure discharge pressure set value is sent to a high pressure discharge pressure adjustment module 510, which determines the deviation between the set value and the exhaust pressure of the high pressure cylinder of the steam turbine obtained by measurement, performs a PID calculation based on the deviation, and outputs the result to control the opening of the intake control valve (ICV) 11 of the low pressure cylinder of the steam turbine, so that the high pressure discharge pressure meets the requirements of the set value. Specifically, an overall command obtained by adding together the output of the control command from the high-pressure discharge pressure regulation module 510 and the output of the feedforward processing module 511 is sent to the signal output module 6, which then sends the sum to the steam turbine controller 8 to control the opening of the intake control valve (ICV) 11 of the low-pressure cylinder of the steam turbine. Here, the high pressure discharge pressure set value module 505 determines the high pressure discharge pressure set value mainly based on the correspondence between the initial stage pressure (representing the load of the steam turbine) and the high pressure discharge pressure or the operator's setting from the man-machine interface processing module 7.

[0030] In addition, frequent operation of the ICV can cause disturbance of the load of the steam turbine and wear of the valve machinery parts, so it is necessary to consider setting a certain dead band in advance when adjusting the high-pressure discharge pressure, and the specific size of the dead band is determined according to the actual conditions of the construction and modified by on-site tests.

[0031] In addition, as shown in FIG. 11, the high discharge pressure is very important for the operation of the nuclear steam turbine, especially for the safety of the last stage blades. In addition to considering the normal regulation control, the present invention also designs an additional protection circuit. In order to prevent the high-pressure discharge pressure from fluctuating due to the excessively fast adjustment change of the FCV extraction flow rate, a feedforward processing module 511 is added to make the ICV quick to respond, and a pressure ratio protection circuit is also taken into consideration, that is, a first pressure ratio low-pass threshold module 506 and a second pressure ratio low-pass threshold module 507 are used to realize the closure of the FCV to avoid further deterioration of the operating condition. Specifically, when the ratio between the exhaust pressure of the high-pressure cylinder of the steam turbine obtained by the above-mentioned measurement and the first stage pressure signal obtained by the measurement is greater than the first pressure ratio threshold, the first pressure ratio low-pass threshold module 506 sends a command to the heat supply flow rate automatic adjustment module 502 to close the extraction fast closing control valve (FCV). The signal output module 6 receives the signal to close the bleed fast closing control valve (FCV) 12 and transmits the received signal to the bleed fast closing control valve (FCV) 12 to realize closure of the bleed fast closing control valve (FCV) 12. When the ratio between the exhaust pressure of the high pressure cylinder of the steam turbine obtained by the above-mentioned measurement and the first stage pressure signal obtained by the measurement is greater than the predetermined second pressure ratio threshold, the second pressure ratio low pass threshold module 507 transmits a signal to the override processing module 509 to close the bleed fast closing control valve (FCV) 12 to realize closure of the bleed fast closing control valve (FCV) 12.

[0032] In addition, as shown in FIG. 11, when the extraction flow rate changes, the heat supply flow rate load compensation algorithm module 512 calculates the electric load value of the unit that needs to be automatically increased or decreased, and transmits it to the steam turbine controller 8 via the signal output module 6 to automatically increase or decrease the electric load, thereby controlling the intake control valve (GV) 10 of the high pressure cylinder of the steam turbine, thereby realizing the interlocking of heat and electricity.

[0033] In an embodiment of the present invention, based on the control system of the above embodiment 1, a process of determining the load value of a steam turbine in a heat supply device and controlling field equipment is shown, as shown in FIG. 12, which includes the following: First, the first stage pressure of the steam turbine is measured by the first stage pressure measuring device 1, and the extraction heat supply flow rate is measured by the extraction heat supply flow rate measuring device 3. Then, the first stage pressure and the extraction heat supply flow rate are collected using the data collection module 4, and the collected signals are sent to the core calculation processing module 5. Then, the core calculation processing module 5 receives the first stage pressure signal, the exhaust pressure of the high pressure cylinder of the steam turbine, and the extraction heat supply flow rate signal sent from the data collection module 4, and determines the load value of the steam turbine using the received signals, and sends the load value to the man-machine interface processing module 7 and the signal output module 6. The man-machine interface processing module 7 receives and displays the load value transmitted from the core arithmetic processing module 5, the signal output module 6 receives the load value of the steam turbine transmitted from the core arithmetic processing module 5 and transmits the load value of the steam turbine to the reactor power control system 14, and finally, the reactor power control system 14 controls the coolant of the reactor 15 based on the load value to enter the steam generator 9, and the steam generator serves as a connecting bridge between the primary circuit and the secondary circuit of the nuclear power plant (the heat transfer tube side of the steam generator is the primary circuit that contains the coolant of the reactor system, and the other side is the turbine generator system (Conventional The secondary circuit is a cooling water secondary circuit for the nuclear reactor core (the primary circuit for the nuclear power plant). The coolant of the nuclear reactor system heats the water of the secondary circuit in the steam generator and absorbs heat from the primary circuit to cool the nuclear reactor core. The water of the secondary circuit is heated in the steam generator and then generates main steam at the outlet of the steam generator. The main steam enters the high-pressure cylinder of the steam turbine unit, and the high-pressure cylinder works to drive the generator to generate electricity. Part of the exhaust gas from the high-pressure cylinder passes through the extraction duct and the shutdown control valve 12 and then directly enters the heat supply network heater 13. The heat supply network heater 13 heats the heat supply circulating water that has entered its interior, and finally heats the circulating water to realize heat supply to the outside.

[0034] In the embodiment of the present invention, the core processing module 5 is used to receive the first stage pressure signal and the extraction heat supply flow rate signal sent from the data collection module 4, and determine the load value of the steam turbine using the received signals, as shown in FIG. 12. FIG. 12 is a detailed functional block diagram of the inside of core arithmetic processing module 5, and explains the detailed relationship between module 5 and modules 4 and 7. Referring to FIG. 12, module 5 is responsible for the essential computing processing tasks, and the first stage pressure signal of the steam turbine from the data collection module 4 is simultaneously sent to the first curve module 513, the second curve module 514, and the third curve module 515, among which, the first curve module 513 is set with a non-extraction heat supply curve (i.e., curve 1), the second curve module 514 is set with curve 2, and the third curve module 515 is set with curve 3. Of the three curves according to this embodiment, one curve represents a non-bleed heat supply curve (a relationship curve between the initial stage pressure and the steam turbine load in a non-bleed heat supply operating condition), and the other two curves represent relationship curves between the initial stage pressure and the steam turbine load corresponding to two types of extraction flow rate operating conditions (for example, 500 t / h and 1000 t / h), and the selection of the extraction flow rate operating condition needs to be determined by calculation, taking into consideration the effects of the maximum extraction flow rate and the load curve deviation in a comprehensive manner. The input end of the curve is the first stage pressure of the steam turbine, and the output is the load value of the steam turbine linearly transformed based on the curve.

[0035] Further, as shown in FIG. 12, the switching selection of the non-bleed heat supply curve (i.e., curve 1) is achieved by the first switching module 516, the first input port 441 and the second input port 442 respectively represent the two inputs (outputs from the two curves respectively) of the first switching module 516, the first control port 443 is the control end of the first switching module 516, when the first control port 443 is logic "0", the first switching module 516 outputs the load value of the non-bleed heat supply curve, when the first control port 443 is logic "1", the first switching module 516 outputs the load value of the curve of the second curve module 514, in order to avoid interference in the process of the first input port 441 and the second input port 442 switching each other, the first switching module 516 can realize the mutual tracking of the data of the two input ends to ensure bumpless in the switching process. For example, when the first switching module 516 works with the first input port 441, the second input port 442 automatically tracks the value of the first input port 441; when the first switching module 516 detects that the first control port 443 is at logic "1", it quickly switches from the first input port 441 to the second input port 442 to work, and the second input port 442 tracks the value of the first input port 441 all the time, so that the output of the first switching module 516 does not change at the moment of switching, and after switching, its output gradually changes from the value of the first input port 441 to the value of the second input port 442 at a preset rate (e.g., 5% / min, specifically determined according to the actual situation of the construction), and vice versa.

[0036] Furthermore, as shown in FIG. 12, the operating principle of the second switching module 517 is the same as that of the first switching module 516, and the second switching module 517 is used to select whether the system operates on curve 2 or curve 3. The switching commands of the first switching module 516 and the second switching module 517 are respectively from the first flow rate threshold module 518 and the second flow rate threshold module 519, and the principle of generating the switching commands is explained by an example as follows.

[0037] Assuming that the three curves are relationship curves between the first stage pressure and the steam turbine load corresponding to three operating conditions, namely, a non-extraction heat supply operating condition, an extraction amount of 500 t / h, and 1000 t / h, respectively, and assuming that the setting value of the first flow rate threshold module 518 at this time operates at more than 250 t / h, and the setting value of the second flow rate threshold module 519 operates at more than 750 t / h, as shown in Figures 13, 14, and 15, an example of the operating process is as follows: When the unit is to supply extracted heat, the operator first issues a heat supply on / off command via the man-machine interface module 7, and the heat supply command enters the heat supply on / off command processing module 520 for further calculation and processing. When the conditions for supplying heat are met (preparation complete), the heat supply on / off command processing module 520 outputs "1", indicating that heat supply is on. When the extraction heat supply flow rate is lower than 250 t / h, neither the first flow rate threshold module 518 nor the second flow rate threshold module 519 operates, and the values ​​of the first control port 443 and the second control port 453 are both "0", causing the first switching module 516 and the second switching module 517 to output the values ​​of the first input port 441 and the third input port 451, respectively. In this way, when the load value of the steam turbine of the non-extraction heat supply curve is output, and the extraction heat supply flow rate is greater than 250 t / h and less than 750 t / h, the first flow rate threshold module 518 operates to output "1", and the output of the heat supply input / output command processing module 520 at this time is also "1", and the second flow rate threshold module 519 is also "1" after performing the "NOT" operation, so the "AND" logic gate after the first flow rate threshold module 518 outputs "1", and thus the first control port 443 corresponding to the first switching module 516 is "1", causing the first switching module 516 to switch from the first input port 441 to the second input port 442, that is, to switch from the non-extraction heat supply curve to the 500 t / h curve and operate. Similarly, when the extraction heat supply flow rate exceeds 750 t / h, the second flow rate threshold module 519 operates and outputs "1", and since the output of the heat supply on / off command processing module 520 at this time is also "1", the "AND" logic gate after the second flow rate threshold module 519 outputs "1", and thus the second control port 453 corresponding to the second switching module 517 is "1", and the output of the second switching module 517 is switched from the third input port 451 to the fourth input port 452, and the curve is switched from the 500 t / h curve to the 1000 t / h curve and operated. The smart device can not only automatically complete the selection of the load matching curve according to different extraction heat supply amounts, but also display which curve the system is currently running on in real time on the man-machine interface, making it easy for operators to monitor.

[0038] In short, the control system of the embodiment of the present invention realizes intelligent adjustment of system equipment related to extraction heat supply, the exhaust pressure of the high-pressure cylinder, and the electrical load of the steam turbine, etc., thereby reducing the probability of errors caused by human factors and improving the degree of automation and the operational reliability and safety of the equipment. In addition, the system adjustment method is flexible and has a fast response, making the operation of the heat supply unit safer, more efficient and economical. The control system of the embodiment also significantly reduces the error of the system operation parameters due to the original single curve, and improves the system operation stability of the reactor system during the heat supply period of the nuclear power unit. In addition, by bumplessly switching between multiple operation control curves, disturbances to the primary circuit parameters of the reactor during the heat supply load change period can be avoided, and the operational safety and reliability of the nuclear power unit during the heat supply period can be improved. Example 3

[0039] As shown in FIG. 16, a method of controlling an extraction fast-closing control valve (FCV) 12, an intake control valve (GV) 10 of a high-pressure cylinder of a steam turbine, and an intake control valve (ICV) 11 of a low-pressure cylinder of a steam turbine in a heat supply device corresponding to the system according to the second embodiment is as follows: Step 1: acquiring a first stage pressure signal of a steam turbine, an exhaust pressure signal of a high pressure cylinder of the steam turbine, and an extraction heat supply flow rate signal obtained by measurement, as well as an extraction heat supply flow rate setting value and a high pressure discharge pressure setting value corresponding to a load demand of a heat supply network; determining a deviation between the extraction heat supply flow rate signal and the extraction heat supply flow rate set value using the extraction heat supply flow rate set value and the extraction heat supply flow rate signal, and determining a deviation between the exhaust pressure signal and the high pressure discharge pressure set value using the high pressure discharge pressure set value and an exhaust pressure signal of a high pressure cylinder of the steam turbine; and step 3 of controlling an extraction fast closing control valve (FCV) 12, an intake control valve (ICV) 11 of a low pressure cylinder of the steam turbine, and an intake control valve (GV) 10 of a high pressure cylinder of the steam turbine based on the deviation and the extraction heat supply flow signal.

[0040] In an embodiment of the present invention, the step of controlling the extraction fast closing control valve (FCV) 12, the intake control valve (ICV) 11 of the low pressure cylinder of the steam turbine, and the intake control valve (GV) 10 of the high pressure cylinder of the steam turbine based on the deviation and the extraction heat supply flow rate signal respectively includes: controlling a bleed air fast closing control valve (FCV) 12 based on a deviation between the bleed air heat supply flow rate signal and the bleed air heat supply flow rate set value; controlling an intake control valve (ICV) 11 of a low pressure cylinder of a steam turbine based on a deviation between the exhaust pressure signal and the high pressure discharge pressure setpoint; determining the electric load value of the unit that needs to be automatically increased or decreased based on the extraction heat supply flow signal, and controlling the intake control valve (GV) 10 of the high pressure cylinder of the steam turbine.

[0041] In summary, the control method according to an embodiment of the present invention realizes intelligent adjustment of system equipment related to extraction heat supply, the exhaust pressure of the high-pressure cylinder, and the electrical load of the steam turbine, thereby reducing the probability of errors caused by human factors in manual operation, improving the degree of automation and the operational reliability and safety of the equipment, and the system adjustment method is flexible and responsive, making the operation of the heat supply unit safer, more efficient and more economical. Example 4

[0042] As shown in FIG. 17, a method for controlling a load of a steam turbine in a heat supply device corresponding to a system according to the second embodiment includes the following steps: Step B1: collecting the first stage pressure signal and the extraction heat supply flow rate signal using a data collection module 4, and performing pre-processing on the collected first stage pressure signal and the extracted heat supply flow rate signal; Step B2: selecting a load curve that matches the extraction heat supply flow rate based on the pre-processed first stage pressure signal and the extraction heat supply flow rate signal to determine a load value of the steam turbine; and step B3 of adjusting the output of the primary circuit of the reactor based on the load value of the steam turbine.

[0043] In an embodiment of the present invention, the step of selecting a load curve that matches the extraction heat supply flow rate based on the collected pre-processed first stage pressure signal and the extraction heat supply flow rate signal of the steam turbine to determine the load value of the steam turbine includes: determining a switch command output from the threshold module based on a preset extraction heat supply flow threshold and the magnitude of the collected extraction heat supply flow signal; determining a load value of the steam turbine corresponding to the first stage pressure signal by selecting a load curve that matches the extraction heat supply flow rate based on the switching command;

[0044] In an embodiment of the present invention, the load curve is determined according to the operating condition of the extraction heat supply flow rate.

[0045] In short, the control method of this embodiment reduces errors in system operation parameters, improves the system operation stability of the reactor system during the heat supply period of the nuclear power unit, and by bumpless switching of multiple operation control curves, avoids disturbances in the primary circuit parameters of the reactor during the heat supply load change period, thereby improving the operation safety and reliability of the nuclear power unit during the heat supply period.

[0046] In the description of this specification, any reference to terms such as "one embodiment," "some embodiments," "examples," "specific examples," or "some examples" means that the particular feature, structure, material, or characteristic described in connection with that embodiment or example is included in at least one embodiment or example of the present invention. In this specification, general descriptions of the above terms do not necessarily refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Furthermore, those skilled in the art may make combinations and combinations of different embodiments and examples and features of different embodiments and examples described herein without mutual inconsistency.

[0047] Any process or method description depicted in a flowchart or otherwise herein illustrates modules, segments, or portions that contain executable command code for implementing one or more particular logical functions or process steps, and the scope of the embodiments of the invention includes alternative implementations, including performing functions out of the order shown or discussed herein, in an essentially concurrent manner or in reverse order depending on such functions.

[0048] Although the embodiments of the present invention have been described above, the above embodiments do not limit the present invention, and changes, modifications, substitutions, and variations can be made to the above embodiments within the scope of the present invention. [Explanation of symbols]

[0049] 1. First stage pressure measuring device 2. High-pressure discharge pressure measuring device 3 Extraction heat supply flow rate measuring device 4 Data Collection Module 5-core processing module 6 Signal Output Module 7 Man-machine interface processing module 8 Steam Turbine Controller 9. Nuclear Reactor Steam Generator 10. Steam turbine high pressure cylinder intake control valve (GV) 11 Intake control valve (ICV) for low pressure cylinder of steam turbine 12 Bleed fast closing control valve (FCV) 13 Heat supply network heater 14 Nuclear Reactor Power Control System 15 nuclear reactor 501 Extraction flow rate setpoint generation module 502 Automatic Heat Supply Flow Control Module 503 Manual / Automatic Module 504 Override Control Module 505 High Pressure Discharge Pressure Setpoint Generation Module 506 First Pressure Ratio Low Pass Threshold Module 507 Second Pressure Ratio Low Pass Threshold Module 508 Override Function Trigger Condition Module 509 Override Processing Module 510 High Pressure Discharge Pressure Regulation Module 511 Feedforward Module 512 Heat Supply Flow Load Compensation Algorithm Module 513 First Curve Module 514 Second Curve Module 515 Third Curve Module 516 First Switching Module 517 Second Switching Module 518 First Flow Threshold Module 519 Second Flow Threshold Module 520 Heat supply on / off command processing module 441 First input port 442 Second Input Port 443 First Control Port 451 3rd input port 452 4th input port 453 Secondary Control Port

Claims

1. A control system for a heat supply device for a nuclear power plant, comprising: a first stage pressure measuring device for measuring a first stage pressure of the steam turbine to obtain a first stage pressure signal; a high pressure discharge pressure measuring device for measuring an exhaust pressure of a high pressure cylinder of the steam turbine to obtain an exhaust pressure signal; a bleed air heat supply flow measurement device for measuring the bleed air heat supply flow rate to obtain a bleed air heat supply flow rate signal; a data collection module for collecting the first stage pressure signal, the exhaust pressure signal, and the bleed heat supply flow rate signal obtained by measurement, and transmitting the collected first stage pressure signal, the exhaust pressure signal, and the bleed heat supply flow rate signal to a core calculation processing module; a core calculation processing module for receiving the initial stage pressure signal, the exhaust pressure signal, and the extraction heat supply flow rate signal transmitted from the data collection module, generating an operation command for each valve in the heat supply device based on the initial stage pressure signal, the exhaust pressure signal, and the extraction heat supply flow rate signal, or determining a load value of the steam turbine using the received signals, and transmitting the operation command or the load value of the steam turbine to a signal output module; a signal output module for receiving the operation command or the load value of the steam turbine from the core calculation processing module and transmitting the operation command or the load value of the steam turbine to a field device for control, The core processing module includes: an extraction air flow rate setting value generation module for transmitting a preset flow rate setting value or a setting value provided by an operator via a man-machine interface module to the heat supply flow rate automatic adjustment module according to a load demand of the heat supply network; the heat supply flow rate automatic adjustment module for receiving a set value sent from the extraction air flow rate set value generation module, determining a deviation between the extraction air heat supply flow rate obtained by measurement and the set value, performing a PID calculation based on the deviation, and sending the calculation result to a manual / automatic module; and a manual / automatic module for receiving a calculation result transmitted from the heat supply flow rate automatic adjustment module and controlling an extraction fast closing control valve FCV in the heat supply device based on the calculation result.

2. The control system for the nuclear power plant heat supply device further includes a man-machine interface processing module for exchanging information with the core arithmetic processing module, 2. The control system for a heat supply device for a nuclear power plant according to claim 1, wherein the information exchange includes manual operation commands, setting value input, signal display, alarm processing and function switching in a core computing process.

3. Before generating an operation command for each valve in the heat supply device based on the first stage pressure signal, the exhaust pressure signal, and the extraction heat supply flow rate signal, or before determining a load value of the steam turbine using the received signals, further performing pre-processing on the received first stage pressure signal, exhaust pressure signal, and extraction heat supply flow rate signal; 3. The control system for a heat supply device for a nuclear power plant according to claim 2, wherein the pre-processing includes performing 2 / 3 majority redundancy processing on the initial stage pressure signal, the exhaust pressure signal, and the extraction heat supply flow rate signal collected by a plurality of channels, respectively, to determine whether a measurement range corresponding to the collected signals exceeds a preset measurement range and whether a value of the collected signals is greater than a preset signal threshold, and sending an alarm signal to a man-machine interface processing module when the measurement range corresponding to the collected signals exceeds the preset measurement range or when the value of the collected signals is greater than the preset signal threshold.

4. The core processing module includes: a high pressure discharge pressure set point generating module for transmitting a preset high pressure discharge pressure set point based on a design requirement of the steam turbine or a set point provided by an operator via the man-machine interface module to the high pressure discharge pressure regulating module; 3. The control system for a heat supply device for a nuclear power plant according to claim 2, further comprising: a high-pressure discharge pressure adjustment module for receiving an exhaust pressure of a high-pressure cylinder of a steam turbine obtained by measurement and an exhaust pressure set value transmitted from a high-pressure discharge pressure set value generation module, determining a deviation between the exhaust pressure obtained by measurement and the set value, performing a PID calculation based on the deviation to obtain a calculation result, and controlling an intake control valve ICV of a low-pressure cylinder of the steam turbine based on the calculation result.

5. The core processing module includes: a first pressure ratio low-pass threshold module for comparing a ratio between an exhaust pressure of a high pressure cylinder of the steam turbine obtained by measurement and an initial stage pressure signal obtained by measurement with a preset first pressure ratio threshold, and sending a signal to close the extraction fast closing control valve to a heat supply flow rate automatic adjustment module when the ratio between the exhaust pressure of the high pressure cylinder of the steam turbine obtained by measurement and the initial stage pressure signal obtained by measurement is greater than the preset first pressure ratio threshold, thereby realizing the closure of the extraction fast closing control valve; a second pressure ratio low pass threshold module for comparing a ratio between an exhaust pressure of a high pressure cylinder of the steam turbine obtained by measurement and an initial stage pressure signal obtained by measurement with a second pressure ratio threshold value set in advance, and sending a signal to close the extraction fast closing control valve to an override processing module when the ratio between the exhaust pressure of the high pressure cylinder of the steam turbine obtained by measurement and the initial stage pressure signal obtained by measurement is greater than the second pressure ratio threshold value set in advance, to realize quick closing of the extraction fast closing control valve; an override processing module for sending a control command to an override control module when receiving a signal sent from an override function trigger condition module, the override processing module including heat supply exit, turbine trip, and OPC operation; 2. The control system for a nuclear power plant heat supply device according to claim 1, further comprising: an override control module provided at an input end of the extraction fast closing control valve, for receiving a control command sent from the override processing module, and controlling the extraction fast closing control valve based on the control command.

6. The core processing module includes:

5. The control system for a nuclear power plant heat supply device according to claim 4, further comprising a feedforward module for pre-operating an intake control valve of a low-pressure cylinder of the steam turbine in pre-response to a change in the extraction heat supply flow rate obtained by the measurement so that the high-pressure discharge pressure is quickly adjusted.

7. The core processing module includes: a heat supply flow load compensation algorithm module for calculating and generating control commands to adjust the heat supply and automatically increase or decrease the electrical load of the unit when the total load of the steam turbine is to be maintained; 2. The control system for a heat supply device for a nuclear power plant according to claim 1, wherein the increase or decrease in the electric load is achieved by a steam turbine controller operating a steam turbine high pressure regulating valve.

8. The core processing module includes: a first curve module, which determines a load value of the steam turbine corresponding to a first stage pressure obtained by measurement based on the load curve 1, the first curve module having a load curve 1 obtained in advance; a second curve module for determining a load value of the steam turbine corresponding to the first stage pressure obtained by measurement based on the load curve 2, the second curve module being set in advance; a third curve module, which is configured to determine a load value of the steam turbine corresponding to the first stage pressure obtained by measurement based on the load curve 3, the third curve module being configured to determine a load value of the steam turbine corresponding to the first stage pressure obtained by measurement based on the load curve 3; a first switching module for receiving a switching signal and switching between the pre-obtained load curve 1 and the pre-obtained load curve 2; a second switching module for receiving a switching signal to switch between the pre-obtained load curve 2 and the pre-obtained load curve 3; 2. The control system for a nuclear power plant heat supply device according to claim 1, wherein the number of the load curves is determined according to the type of operation status of the extraction heat supply flow rate.

9. The core processing module includes: a first flow rate threshold module for comparing a magnitude of the measured bleed air heat supply flow rate with a preset threshold in a first flow rate threshold module, and sending a command to the first switching module to switch from the load curve 1 to the load curve 2 if the measured bleed air heat supply flow rate is greater than the preset threshold; a second flow rate threshold module for comparing a magnitude of the measured bleed air heat supply flow rate with a preset threshold in a second flow rate threshold module, and sending a command to the second switching module to switch from the load curve 2 to the load curve 3 if the measured bleed air heat supply flow rate is greater than the preset threshold; 9. The control system for a heat supply device for a nuclear power plant according to claim 8, further comprising a heat supply on / off command processing module for determining whether the heat supply device satisfies a heat supply on condition in response to a heat supply on / off command from an operator, and transmitting a heat supply on / off command when the condition is satisfied.

10. The first switching module and the second switching module are further used to realize mutual automatic tracking of load curves before and after switching; The number of flow threshold modules corresponds to the number of switching modules; 9. The control system for a nuclear power plant heat supply device according to claim 8, wherein the number of flow rate threshold modules is determined according to the type of operation status of the extraction heat supply flow rate.

11. A method for controlling a heat supply apparatus for a nuclear power plant by the control system for the heat supply apparatus for a nuclear power plant according to any one of claims 1 to 7, Obtaining a first stage pressure signal of the steam turbine, an exhaust pressure signal of a high pressure cylinder of the steam turbine, and an extraction heat supply flow rate signal obtained by measurement, as well as an extraction heat supply flow rate set value and a high pressure discharge pressure set value corresponding to a load demand of the heat supply network; determining a deviation between the extraction heat supply flow rate signal and the extraction heat supply flow rate set value using the extraction heat supply flow rate set value and the extraction heat supply flow rate signal, and determining a deviation between the exhaust pressure signal and the high pressure discharge pressure set value using the high pressure discharge pressure set value and an exhaust pressure signal of a high pressure cylinder of the steam turbine; and controlling an extraction fast closing control valve, an intake control valve of a low pressure cylinder of the steam turbine, and an intake control valve of a high pressure cylinder of the steam turbine based on the deviation and an extraction heat supply flow rate signal.

12. A method for controlling a heat supply apparatus for a nuclear power plant by the control system for the heat supply apparatus for a nuclear power plant according to any one of claims 1 to 3 and 8 to 10, collecting the first stage pressure signal and the extraction heat supply flow rate signal using a data collection module, and performing pre-processing on the collected first stage pressure signal and the extracted heat supply flow rate signal; determining a load value of the steam turbine by selecting a load curve that matches the extraction heat supply flow rate based on the pre-processed first stage pressure signal and the extraction heat supply flow rate signal; and adjusting a reactor output based on a load value of the steam turbine.

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