Reactor-turbine unit control method and apparatus

Abstract

A reactor-turbine unit control method and apparatus, which belong to the technical field of nuclear power. The reactor-turbine unit control method comprises: acquiring the type of a steam turbine and a control strategy for a nuclear power unit, wherein the nuclear power unit comprises a reactor-turbine unit (S100); on the basis of the type of the steam turbine and the control strategy, calculating an energy balance signal and a heat signal, wherein the energy balance signal is used for indicating the minimum energy required for the operation of the steam turbine, and the heat signal is used for indicating the energy generated by a reactor (S200); on the basis of the energy balance signal and the heat signal, obtaining a feedforward signal (S300); and on the basis of the feedforward signal, controlling a rod position action of a control rod (S400). The reactor-turbine unit control method can improve the response speed and adjustment capability of a nuclear power unit when facing rapid load changes.

Description

Stacker control methods and devices Technical Field

[0001] This application relates to the field of nuclear power technology, and in particular to a reactor control method and apparatus. Background Technology

[0002] Nuclear energy, as a safe, clean, low-carbon, and high-energy-density strategic energy source, occupies an important position in the global energy structure, ensuring national energy security and promoting green and low-carbon development. Currently, nuclear power units have become an indispensable part of the power supply system, playing a crucial role, especially in providing stable and large-scale power. However, with the rapid development of renewable energy and the increasing demand for flexibility resources in the power system, the flexibility issues of nuclear power units are becoming increasingly apparent. Because nuclear power units are designed to achieve efficient and stable power output, they suffer from insufficient regulation capacity when responding to rapidly changing load demands in the power system.

[0003] Existing large nuclear power units generally adopt G-mode control, a reactor control mode for large pressurized water reactor nuclear power units, also known as "reactor-following" operation mode. In this mode, the turbine automatically adjusts its steam flow to change its power output based on external load commands, and the reactor adjusts its nuclear power output accordingly. Although this method is commonly used in large reactors, the reactor passively following turbine load changes can easily lead to load mismatches between the primary and secondary loops, causing fluctuations in main steam pressure and affecting the overall operational stability and safety of the unit. Summary of the Invention

[0004] The main objective of this application is to propose a reactor control method and apparatus, which aims to improve the response speed and adjustment capability of nuclear power units in the face of rapid load changes.

[0005] To achieve the above objectives, a first aspect of this application proposes a reactor control method, wherein the reactor includes a reactor, a turbine, and control rods, the control rods being used to adjust the nuclear power and the average temperature of the reactor, and the turbine being used to convert the thermal energy generated by the reactor into mechanical energy, the method comprising:

[0006] The type of the steam turbine and the control strategy of the nuclear power unit, including the reactor, are obtained.

[0007] Based on the type of steam turbine and the control strategy, an energy balance signal and a heat signal are calculated. The energy balance signal is used to indicate the minimum energy required for the steam turbine to operate, and the heat signal is used to indicate the energy produced by the reactor.

[0008] The feedforward signal is obtained based on the energy balance signal and the heat signal;

[0009] The position movement of the control rod is controlled according to the feedforward signal.

[0010] In some embodiments, controlling the position movement of the control rod according to the feedforward signal includes:

[0011] Based on the current power measurement value of the steam turbine, the target power setting value of the steam turbine, and the power range core power of the reactor, the power mismatch response signal between the reactor and the steam turbine is obtained;

[0012] Based on the power mismatch response signal, the three-channel nonlinear control signal is determined;

[0013] The three-channel nonlinear control signal and the feedforward signal are processed by the first adder to obtain the first signal;

[0014] The control rod is positioned according to the first signal.

[0015] In some embodiments, determining the three-channel nonlinear control signal based on the power mismatch response signal includes:

[0016] The maximum value between the current power measurement value and the target power setting value is determined as the first power;

[0017] The temperature corresponding to the first power is obtained according to the preset average temperature setpoint function, and the temperature corresponding to the first power is used as the coolant average temperature setpoint. The average temperature setpoint function is used to characterize the relationship between power and temperature.

[0018] The coolant average temperature setpoint, the power mismatch response signal, and the pre-acquired coolant average temperature measurement value are processed by a second adder to obtain the three-channel nonlinear control signal.

[0019] In some embodiments, obtaining the power mismatch response signal between the reactor and the turbine based on the current power measurement value of the turbine, the target power setting value of the turbine, and the nuclear power of the reactor's power range includes:

[0020] Calculate the power deviation between the first power and the core power of the power range, wherein the first power is the maximum value between the current power measurement value and the target power setting value;

[0021] The power deviation is differentiated to obtain the differential signal;

[0022] The differential signal is subjected to a nonlinear gain to obtain a gain differential signal;

[0023] The first power is subjected to a variable gain to obtain a gain power signal;

[0024] Gain correction is performed on the gain differential signal and the gain power signal to obtain the power mismatch response signal.

[0025] In some embodiments, the turbine is a turbine with a regulating stage, and the control strategy of the nuclear power unit is a control strategy with both main steam pressure and primary loop temperature constant.

[0026] The calculation of energy balance signals and heat signals based on the type of steam turbine and the control strategy of the nuclear power unit includes:

[0027] The regulating stage pressure, main steam pressure setpoint, main steam pressure measured value, steam generator pressure, and primary loop heat storage coefficient of the steam turbine with regulating stage are obtained.

[0028] The energy balance signal is obtained by calculating based on the regulating stage pressure, the main steam pressure setpoint, and the measured main steam pressure.

[0029] The heat signal is obtained by calculating based on the regulating stage pressure, the steam generator pressure, and the primary loop heat storage coefficient.

[0030] In some embodiments, the turbine is a turbine with a regulating stage, and the control strategy of the nuclear power unit is a control strategy with constant primary loop temperature;

[0031] The calculation of energy balance signals and heat signals based on the type of steam turbine and the control strategy of the nuclear power unit includes:

[0032] The measured values ​​of the regulating stage pressure, main steam pressure, steam generator pressure, and primary loop heat storage coefficient of the steam turbine with regulating stage are obtained.

[0033] Acquire historical operating data of the nuclear power unit, including turbine power, evaporator water level, and main steam pressure;

[0034] The main steam pressure curve is obtained based on the historical operating data. The main steam pressure curve is a curve showing the change of main steam pressure with the turbine power and the evaporator water level.

[0035] The energy balance signal is obtained by calculating based on the regulating stage pressure, the main steam pressure curve, and the measured value of the main steam pressure.

[0036] The heat signal is obtained by calculating based on the regulating stage pressure, the steam generator pressure, and the primary loop heat storage coefficient.

[0037] In some embodiments, the steam turbine is a steam turbine without a regulating stage, and the control strategy of the nuclear power unit is a control strategy with both main steam pressure and primary loop temperature kept constant.

[0038] The calculation of energy balance signals and heat signals based on the type of steam turbine and the control strategy of the nuclear power unit includes:

[0039] Obtain the relative opening of the turbine valves, the set value of the main steam pressure, the measured value of the main steam pressure, and the primary loop heat storage coefficient of the turbine without a regulating stage;

[0040] The energy balance signal is obtained by calculating based on the relative opening of the turbine valves and the main steam pressure setpoint.

[0041] The heat signal is obtained by calculating based on the relative opening of the turbine valves, the measured value of the main steam pressure, and the primary circuit heat storage coefficient.

[0042] In some embodiments, the steam turbine is a steam turbine without a regulating stage, and the control strategy of the nuclear power unit is a control strategy with a constant primary loop temperature;

[0043] The calculation of energy balance signals and heat signals based on the type of steam turbine and the control strategy of the nuclear power unit includes:

[0044] Obtain the relative opening of the turbine valves, the measured value of the main steam pressure, the steam generator pressure, and the primary loop heat storage coefficient of the turbine without a regulating stage;

[0045] Acquire historical operating data of the nuclear power unit, including turbine power, evaporator water level, and main steam pressure;

[0046] The main steam pressure curve is obtained based on the historical operating data. The main steam pressure curve is a curve showing the change of main steam pressure with the turbine power and the evaporator water level.

[0047] The energy balance signal is obtained by calculating based on the relative opening of the turbine valves and the main steam pressure curve.

[0048] The heat signal is obtained by calculating based on the relative opening of the turbine valves, the measured value of the main steam pressure, the steam generator pressure, and the primary loop heat storage coefficient.

[0049] To achieve the above objectives, a second aspect of this application provides a stacker control device, the device comprising:

[0050] An acquisition module is used to acquire the type of the steam turbine and the control strategy of the nuclear power unit, wherein the nuclear power unit includes the reactor;

[0051] The first calculation module is used to calculate an energy balance signal and a heat signal according to the type of the steam turbine and the control strategy. The energy balance signal is used to indicate the minimum energy required for the steam turbine to operate, and the heat signal is used to indicate the energy produced by the reactor.

[0052] The second calculation module is used to obtain the feedforward signal based on the energy balance signal and the heat signal;

[0053] The rod position control module is used to control the rod position movement of the control rod according to the feedforward signal.

[0054] In some embodiments, the rod position control module includes:

[0055] The power mismatch response signal acquisition submodule is used to obtain the power mismatch response signal between the reactor and the turbine based on the current power measurement value of the turbine, the target power setting value of the turbine, and the power range core power of the reactor.

[0056] The three-channel nonlinear control signal acquisition submodule is used to determine the three-channel nonlinear control signal based on the power mismatch response signal.

[0057] The first addition submodule is used to process the three-channel nonlinear control signal and the feedforward signal through a first adder to obtain a first signal;

[0058] The rod position control submodule is used to control the rod position movement of the control rod according to the first signal.

[0059] To achieve the above objectives, a third aspect of this application provides an electronic device, which includes a memory and a processor. The memory stores a computer program, and the processor executes the computer program to implement the method described in the first aspect.

[0060] To achieve the above objectives, a fourth aspect of the present application provides a computer-readable storage medium storing a computer program that, when executed by a processor, implements the method described in the first aspect.

[0061] The reactor control method and apparatus proposed in this application calculate the corresponding feedforward signal based on the turbine type and the nuclear power unit's control strategy. This feedforward signal is then combined with a three-channel nonlinear control signal to jointly control the position movement of the control rods, thereby adjusting the reactor's nuclear power and achieving coordinated control between the reactor and the turbine. By adding the corresponding feedforward control signal before the rod position control, the differential signal of the main steam pressure deviation can directly affect the rod position control, effectively enhancing the rod position control capability under variable load conditions, thus improving the nuclear power unit's response speed and regulation capability. Attached Figure Description

[0062] Figure 1 is a schematic flowchart of the stacker control method provided in an embodiment of this application;

[0063] Figure 2 is a schematic diagram of the structural principle of the stacker control device provided in an embodiment of this application;

[0064] Figure 3 is a schematic diagram of the stacker control device provided in an embodiment of this application;

[0065] Figure 4 is a schematic diagram of the hardware structure of the electronic device provided in an embodiment of this application.

[0066] In Figure 2, the reference numerals are as follows: 1. Three-channel nonlinear control unit; 11. Coolant average temperature measurement channel; 111. High selector; 112. Amplifier; 113. First filter; 114. Lead-lag compensator; 12. Coolant average temperature setpoint channel; 121. Second filter; 122. Coolant average temperature setpoint unit; 123. Third filter; 13. Power mismatch channel; 131. Third adder; 132. Variable gain controller; 133. Differentiator; 134. Nonlinear gain controller; 135. Multiplier; 14. Second adder; 2. Feedforward control unit; 3. First adder; 4. Rod speed program control unit; 5. Control rod logic control unit; 6. Control rod drive unit. Detailed Implementation

[0067] To make the objectives, technical solutions, and advantages of this application clearer, the following detailed description is provided in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative and not intended to limit the scope of this application.

[0068] It should be noted that although functional modules are divided in the device schematic diagram and a logical order is shown in the flowchart, in some cases, the steps shown or described may be performed in a different order than the module division in the device or the order in the flowchart. The terms "first," "second," etc., in the specification, claims, and the aforementioned drawings are used to distinguish similar objects and are not necessarily used to describe a specific order or sequence.

[0069] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this application belongs. The terminology used herein is for the purpose of describing embodiments of this application only and is not intended to limit this application.

[0070] First, let's analyze some of the terms used in this application:

[0071] Primary Loop: The reactor core generates enormous heat due to nuclear fuel fission. Water pumped into the core by the main pump is heated to 327 degrees Celsius and 155 atmospheres of pressure. This high-temperature, high-pressure water flows through the heat transfer U-tubes in the steam generator, transferring heat through the tube walls to the secondary loop cooling water outside the U-tubes. After releasing heat, it is pumped back to the core for reheating before re-entering the steam generator. This continuous circulation of water within the closed loop is called the primary loop. The main function of the primary loop is to transfer the heat generated by the nuclear reaction to the secondary loop. The reactor coolant circulates in the primary loop, absorbing the heat generated by the nuclear reaction and transferring it to the water in the secondary loop through the steam generator, turning it into steam.

[0072] Secondary loop: In the secondary loop, water outside the U-tube of the steam generator is heated and turns into steam, which drives the steam turbine generator to do work, converting heat energy into electricity. After doing work, the steam enters the condenser to cool, condenses into water, and returns to the steam generator to be reheated into steam. This steam-water cycle is called the secondary loop. The main function of the secondary loop is to convert the heat transferred from the primary loop into electrical energy. The steam generated by the steam generator enters the steam turbine, drives the turbine to rotate, and in turn drives the generator to produce electricity.

[0073] Power mismatch refers to the power imbalance between the primary loop (nuclear reactor) and the secondary loop (steam generator). When the turbine load changes, if the reactor power regulation system cannot respond in time, it will lead to a power imbalance between the primary and secondary loops. For example, when the turbine load suddenly drops, if the reactor power regulation system cannot quickly reduce the reactor power, it will lead to a reduction in the secondary loop steam flow, thus affecting the stable operation of the entire system.

[0074] Temperature mismatch refers to the mismatch between the primary coolant temperature and the secondary steam temperature. In nuclear power plants, the average temperature of the primary coolant needs to be maintained within a stable range to ensure the safe operation of the nuclear reactor. If the secondary steam temperature is too high or too low, it will affect the efficiency of the steam generator, and consequently, the thermal efficiency and economy of the entire system. For example, if the coolant temperature regulation system cannot respond promptly when the turbine load changes, temperature mismatch will occur.

[0075] Distributed Control System (DCS): A new generation of instrument control system based on microprocessors, which adopts the design principles of decentralized control functions, centralized display and operation, and consideration of both decentralized autonomy and comprehensive coordination.

[0076] Existing large nuclear power units generally employ G-mode control, where the turbine automatically adjusts its steam flow to change its power output based on external load commands, and the reactor adjusts its nuclear power output accordingly. Under this control method, because the reactor passively responds to turbine load changes, load mismatches between the primary and secondary loops are prone to occur, leading to fluctuations in main steam pressure. Furthermore, G-mode core control primarily consists of power and temperature mismatches, making it impossible to directly control the main steam temperature in pressurized water reactors with U-shaped evaporators. This results in significant fluctuations in main steam pressure during rapid load changes, impacting the overall operational stability and safety of the unit.

[0077] Based on this, embodiments of this application provide a reactor control method and apparatus, which aim to improve the response speed and adjustment capability of nuclear power units in the face of rapid load changes.

[0078] The stacker control method and apparatus provided in this application are specifically described through the following embodiments. First, the stacker control method in this application is described.

[0079] The reactor control method provided in this application relates to the field of nuclear power technology. The reactor control method provided in this application can be applied to a terminal, a server, or software running on either a terminal or a server. In some embodiments, the terminal can be a smartphone, tablet, laptop, desktop computer, etc.; the server can be configured as an independent physical server, a server cluster or distributed system composed of multiple physical servers, or a cloud server providing basic cloud computing services such as cloud services, cloud databases, cloud computing, cloud functions, cloud storage, network services, cloud communication, middleware services, domain name services, security services, CDN, and big data and artificial intelligence platforms; the software can be an application implementing the reactor control method, but is not limited to the above forms.

[0080] This application can be used in a wide variety of general-purpose or special-purpose computer system environments or configurations. Examples include: personal computers, server computers, handheld or portable devices, tablet devices, multiprocessor systems, microprocessor-based systems, set-top boxes, programmable consumer electronics, network PCs, minicomputers, mainframe computers, and distributed computing environments including any of the above systems or devices. This application can be described in the general context of computer-executable instructions executed by a computer, such as program modules. Generally, program modules include routines, programs, objects, components, data structures, etc., that perform specific tasks or implement specific abstract data types. This application can also be practiced in distributed computing environments where tasks are performed by remote processing devices connected via a communication network. In distributed computing environments, program modules can reside in local and remote computer storage media, including storage devices.

[0081] It should be noted that in all specific embodiments of this application, when processing data related to user identity or characteristics, such as user information, user behavior data, user historical data, and user location information, user permission or consent is obtained first. Furthermore, the collection, use, and processing of this data comply with relevant laws, regulations, and standards. In addition, when embodiments of this application require access to sensitive personal information of users, separate permission or consent from the user is obtained through pop-ups or redirection to confirmation pages. Only after obtaining the user's separate permission or consent is the necessary user-related data required for the proper functioning of these embodiments acquired.

[0082] Figure 1 is an optional flowchart of a reactor control method provided in an embodiment of this application. The reactor includes a reactor, a steam turbine, and control rods. The control rods are used to adjust the nuclear power and the average temperature of the reactor. The steam turbine is used to convert the thermal energy generated by the reactor into mechanical energy. The method in Figure 1 may include, but is not limited to, steps S100 to S400.

[0083] Step S100: Obtain the type of the steam turbine and the control strategy of the nuclear power unit, wherein the nuclear power unit includes the reactor.

[0084] In this embodiment, the turbine type includes turbines with regulating stages and turbines without regulating stages; the control strategy of the nuclear power unit includes a control strategy with both main steam pressure and primary loop temperature constant, and a control strategy with constant primary loop temperature. Specifically, the control strategy with both main steam pressure and primary loop temperature constant is a control strategy where the main steam pressure and the average primary loop temperature remain constant above a certain power plateau (20% FP); the control strategy with constant primary loop temperature is a control strategy where the average primary loop temperature remains constant, and the main steam pressure changes linearly with the unit power.

[0085] Step S200: Calculate an energy balance signal and a heat signal based on the type of steam turbine and the control strategy. The energy balance signal indicates the minimum energy required for the steam turbine to operate, and the heat signal indicates the energy generated by the reactor.

[0086] Based on the type of steam turbine and the control strategy of the nuclear power unit, energy balance signals and heat signals can be obtained. The energy balance signal directly reflects the energy demand of the steam turbine, while the heat signal reflects the heat generated by the reactor core. The difference between the energy balance signal and the heat signal can be used to obtain the energy demand difference between the steam turbine and the reactor.

[0087] Step S300: Obtain the feedforward signal based on the energy balance signal and the heat signal.

[0088] In this embodiment, a feedforward signal is obtained based on the energy balance signal and the heat signal, and the feedforward signal is: G W =G1-G2;

[0089] In the formula, G W G1 is the feedforward signal, G2 is the energy balance signal, and G3 is the heat signal. Subtracting the energy balance signal from the heat signal yields the feedforward signal, which is used to control the control rod.

[0090] Step S400: Control the position movement of the control rod according to the feedforward signal.

[0091] Control rods are used to regulate the nuclear reaction rate. By moving the control rods up and down, the intensity of the nuclear reaction can be increased or decreased, thereby controlling the reactor's thermal power output. Feedforward signals and three-channel nonlinear control signals are applied together to the rod speed program, driving the control rod position movements to adjust the reactor's power output and keep the energy balance signal consistent with the thermal signal.

[0092] This embodiment introduces a corresponding feedforward control signal before the rod position control. This feedforward signal directly affects the rod position control, enabling rapid adjustment of the control rod insertion depth. This, in turn, quickly alters the reactor's reactivity to match the turbine's energy demand. Compared to traditional feedback control, the feedforward signal can predict and compensate for changes in energy demand in advance, thereby accelerating the rate of reactivity change and improving the unit's response speed. Introducing the feedforward signal into the nuclear power unit's control system can effectively enhance the unit's flexibility and control capabilities.

[0093] Figure 2 is a schematic diagram of an optional structure of the stacker control device provided in an embodiment of this application. The device in Figure 2 may include, but is not limited to, a three-channel nonlinear control unit 1, a feedforward control unit 2, a first adder 3, a rod speed program control unit 4, a control rod logic control unit 5, and a control rod drive unit 6.

[0094] The three-channel nonlinear control unit 1 is used to acquire three-channel nonlinear control signals and transmit the three-channel nonlinear control signals to the first adder 3.

[0095] The feedforward control unit 2 is used to acquire the feedforward signal and transmit the feedforward signal to the first adder 3.

[0096] The first adder 3 is used to receive the three-channel nonlinear control signal and the feedforward signal, obtain the first signal based on the three-channel nonlinear control signal and the feedforward signal, and transmit the first signal to the rod speed program control unit 4.

[0097] The rod speed program control unit 4 is used to receive the first signal, obtain the rod speed control signal according to the first signal, and transmit the rod speed control signal to the control rod logic control unit 5.

[0098] The control rod logic control unit 5 is used to receive the rod speed control signal, obtain the rod position control signal based on the rod speed control signal, and transmit the rod position control signal to the control rod drive unit 6.

[0099] The control rod drive unit 6 is used to receive the rod position control signal and control the rod position movement according to the rod position control signal.

[0100] Furthermore, the three-channel nonlinear control unit 1 includes a coolant average temperature measurement channel 11, a coolant average temperature setpoint channel 12, a power mismatch channel 13, and a second adder 14.

[0101] The coolant average temperature measurement channel 11 is used to acquire the average coolant temperature and transmit it to the second adder 14. Specifically, the coolant average temperature measurement channel 11 includes a high selector 111, an amplifier 112, a first filter 113, and a lead-lag compensator 114. The high selector 111 selects the maximum value among several (usually three) thermal loops for control; the average coolant temperature is the arithmetic mean of the hot pipe section (reactor outlet) temperature and the cold pipe section (reactor inlet) temperature. The lead-lag compensator 114 compensates for the response lag caused by the thermal inertia of the coolant average temperature measurement channel 11, providing a lead signal. The first filter 113 filters out thermal noise from the temperature sensor.

[0102] The coolant average temperature setpoint channel 12 is used to obtain the coolant average temperature setpoint based on the maximum value (i.e., the first power) between the current power measurement value of the turbine and the target power setting value of the turbine, and transmits the coolant average temperature setpoint to the second adder 14. Specifically, the coolant average temperature setpoint channel 12 includes a coolant average temperature setpoint unit 122, a second filter 121, and a third filter 123. The input to the coolant average temperature setpoint channel 12 is the larger value between the current power measurement value of the turbine and the target power setting value of the turbine. Then, based on this larger value, a reference value for the coolant average temperature is determined according to the characteristic curve preset by the coolant average temperature setpoint unit 122. The second filter 121 and the third filter 123 are first-order inertial element filters.

[0103] The power mismatch channel 13 is used to obtain a power mismatch response signal based on the first power and the power range nuclear power, and transmit the power mismatch response signal to the second adder 14. When a dynamic power mismatch occurs and the average coolant temperature measurement value has not changed significantly, the power mismatch channel 13 can generate a leading control signal to control the R-bar group, accelerating the nuclear reactor's response to the turbine load demand. Specifically, the power mismatch channel 13 includes a variable gain controller 132, a differentiator 133, a nonlinear gain controller 134, a multiplier 135, and a third adder 131. The third adder 131 is used to calculate the power deviation; the differentiator 133 is used to perform a differential operation on the power deviation and generate a differential signal; the nonlinear gain controller 134 is used to perform a nonlinear gain on the differential signal to obtain a gain differential signal; the variable gain controller 132 is used to perform a variable gain on the first power to obtain a gain power signal; the multiplier 135 is used to perform gain correction on the gain differential signal obtained after the nonlinear gain controller 134 and the gain power signal obtained after the first power is processed by the variable gain controller 132 to obtain a power mismatch response signal, and transmit the power mismatch response signal to the second adder 14. When the load changes, a power deviation occurs between the first power and the core power of the power range. The third adder 131 calculates the power deviation, and the differentiator 133 performs a differential operation on the power deviation to generate a differential signal. The signal after the nonlinear gain controller 134 and the signal after the variable gain controller 132 are subjected to gain correction in the multiplier 135, and then transmitted to the second adder 14. Due to the function of the differentiator 133, the power mismatch channel 13 provides a fast response signal according to the rate of change of power deviation during the transition process. If the power deviation changes very slowly, the power mismatch channel 13 will have a weak effect. If there is no power deviation or the power deviation does not change, the power mismatch channel 13 will not work.

[0104] The second adder 14 is used to receive the average coolant temperature, the average coolant temperature setpoint, and the power mismatch response signal, obtain a three-channel nonlinear control signal based on the average coolant temperature, the average coolant temperature setpoint, and the power mismatch response signal, and transmit the three-channel nonlinear control signal to the first adder 3.

[0105] In some embodiments, step S200 may include, but is not limited to, the following steps:

[0106] The type of steam turbine is a steam turbine with a regulating stage, and the control strategy of the nuclear power unit is a control strategy with both main steam pressure and primary loop temperature being constant.

[0107] The calculation of energy balance signals and heat signals based on the type of steam turbine and the control strategy of the nuclear power unit includes:

[0108] The regulating stage pressure, main steam pressure setpoint, main steam pressure measured value, steam generator pressure, and primary loop heat storage coefficient of the steam turbine with regulating stage are obtained.

[0109] The energy balance signal is obtained by calculating based on the regulating stage pressure, the main steam pressure setpoint, and the measured main steam pressure.

[0110] The heat signal is obtained by calculating based on the regulating stage pressure, the steam generator pressure, and the primary loop heat storage coefficient.

[0111] Based on whether the flow area of ​​each stage varies with the load, steam turbines can be divided into steam turbines with a regulating stage and steam turbines without a regulating stage. Steam turbines with a regulating stage adjust the steam flow rate through adjustable nozzles, thereby regulating the turbine's output power. The regulating stage is the first stage of the turbine that performs power, and it can regulate the turbine load by adjusting the flow area. Steam turbines without a regulating stage use full-circumference steam inlet in the first stage, and their output power mainly depends on the amount of steam entering the turbine, which is usually controlled by the relative opening of the turbine valves.

[0112] First, the regulating stage pressure, main steam pressure setpoint, measured main steam pressure, steam generator pressure, and primary loop heat storage coefficient of the turbine with regulating stage are obtained. Specifically, the regulating stage pressure, main steam pressure setpoint, measured main steam pressure, and steam generator pressure can all be directly obtained from the unit's distributed control system (DCS). The primary loop heat storage coefficient is a parameter to be determined. The steps to obtain the primary loop heat storage coefficient are as follows: operate the nuclear power unit under stable operating conditions; deactivate the automatic control logic of the reactor power, automatic control logic of the water level, and automatic control logic of the turbine valves; input a step disturbance signal to the turbine valves and record the start time of the test; record the main steam flow rate and main steam pressure during the test; when the unit load and main steam pressure tend to stabilize, the test ends and the end time of the test is recorded; obtain the primary loop heat storage coefficient based on the test start time, main steam flow rate, main steam pressure, and test end time.

[0113] In some preferred embodiments, the primary loop heat storage coefficient can be obtained according to the following formula:

[0114] In the formula, C R Let D be the primary loop heat storage coefficient, t be the test time, t0 be the start time of the test, t1 be the end time of the test, and D be the secondary loop heat storage coefficient. t Main steam flow rate, P T The measured value of the main steam pressure.

[0115] The energy balance signal is obtained based on the regulating stage pressure, the main steam pressure setpoint, and the measured main steam pressure. The energy balance signal is as follows:

[0116] In the formula, G1 is the energy balance signal, and P S The main steam pressure setpoint, P1 is the regulating stage pressure, P T The measured value of the main steam pressure.

[0117] The heat signal is obtained based on the regulating stage pressure, the primary loop heat storage coefficient, and the steam generator pressure. The heat signal is:

[0118] In the formula, G2 is the heat signal, Pd is the steam generator pressure, and C R The primary loop heat storage coefficient is denoted as .

[0119] In some embodiments, step S200 may include, but is not limited to, the following steps:

[0120] The type of steam turbine is a steam turbine with a regulating stage, and the control strategy of the nuclear power unit is a control strategy with constant primary loop temperature;

[0121] The calculation of energy balance signals and heat signals based on the type of steam turbine and the control strategy of the nuclear power unit includes:

[0122] The measured values ​​of the regulating stage pressure, main steam pressure, steam generator pressure, and primary loop heat storage coefficient of the steam turbine with regulating stage are obtained.

[0123] Acquire historical operating data of the nuclear power unit, including turbine power, evaporator water level, and main steam pressure;

[0124] The main steam pressure curve is obtained based on the historical operating data. The main steam pressure curve is a curve showing the change of main steam pressure with the turbine power and the evaporator water level.

[0125] The energy balance signal is obtained by calculating based on the regulating stage pressure, the main steam pressure curve, and the measured value of the main steam pressure.

[0126] The heat signal is obtained by calculating based on the regulating stage pressure, the steam generator pressure, and the primary loop heat storage coefficient.

[0127] First, obtain the measured values ​​of the regulating stage pressure, main steam pressure, steam generator pressure, and primary loop heat storage coefficient of the steam turbine with regulating stage.

[0128] Then, historical operating data of the nuclear power unit is obtained, including historical data such as turbine power, evaporator water level and main steam pressure. After preprocessing the historical operating data, the expression of the main steam pressure curve fitted by regression method is: f(P,W).

[0129] The energy balance signal is obtained based on the regulating stage pressure, the main steam pressure curve, and the measured value of the main steam pressure. The energy balance signal is as follows:

[0130] In the formula, G1 is the energy balance signal, f(P,W) is the function corresponding to the main steam pressure curve, P1 is the regulating stage pressure, and P T The measured value of the main steam pressure is given, where P is the unit load and W is the evaporator water level.

[0131] A heat signal is obtained based on the regulating stage pressure, the primary loop heat storage coefficient, and the steam generator pressure; the heat signal is:

[0132] In the formula, G2 is the heat signal, and P d C is the pressure of the steam generator. R The primary loop heat storage coefficient is denoted as .

[0133] In some embodiments, step S200 may include, but is not limited to, the following steps:

[0134] The type of steam turbine is a steam turbine without a regulating stage, and the control strategy of the nuclear power unit is a control strategy with both main steam pressure and primary loop temperature being constant.

[0135] The calculation of energy balance signals and heat signals based on the type of steam turbine and the control strategy of the nuclear power unit includes:

[0136] Obtain the relative opening of the turbine valves, the set value of the main steam pressure, the measured value of the main steam pressure, and the primary loop heat storage coefficient of the turbine without a regulating stage;

[0137] The energy balance signal is obtained by calculating based on the relative opening of the turbine valves and the main steam pressure setpoint.

[0138] The heat signal is obtained by calculating based on the relative opening of the turbine valves, the measured value of the main steam pressure, and the primary circuit heat storage coefficient.

[0139] First, obtain the relative opening degree of the turbine valves, the main steam pressure setpoint, the measured main steam pressure, and the primary loop heat storage coefficient for a turbine without a regulating stage. Specifically, the relative opening degree of the turbine valves, the main steam pressure setpoint, and the measured main steam pressure can all be obtained directly from the unit's DCS.

[0140] The energy balance signal is calculated based on the relative opening of the turbine valves and the main steam pressure setpoint. The energy balance signal is: G1=U1×P S ;

[0141] In the formula, G1 is the energy balance signal, U1 is the relative opening degree of the turbine valve, and P S Main steam pressure setpoint.

[0142] The heat signal is calculated based on the relative opening of the turbine valves, the measured value of the main steam pressure, and the primary loop heat storage coefficient. The heat signal is:

[0143] In the formula, G2 is the heat signal, and P T The measured value of the main steam pressure, C R The primary loop heat storage coefficient is denoted as .

[0144] In some embodiments, step S200 may include, but is not limited to, the following steps:

[0145] The type of steam turbine is a steam turbine without a regulating stage, and the control strategy of the nuclear power unit is a control strategy with constant primary loop temperature;

[0146] The calculation of energy balance signals and heat signals based on the type of steam turbine and the control strategy of the nuclear power unit includes:

[0147] Obtain the relative opening of the turbine valves, the measured value of the main steam pressure, the steam generator pressure, and the primary loop heat storage coefficient of the turbine without a regulating stage;

[0148] Acquire historical operating data of the nuclear power unit, including turbine power, evaporator water level, and main steam pressure;

[0149] The main steam pressure curve is obtained based on the historical operating data. The main steam pressure curve is a curve showing the change of main steam pressure with the turbine power and the evaporator water level.

[0150] The energy balance signal is obtained by calculating based on the relative opening of the turbine valves and the main steam pressure curve.

[0151] The heat signal is obtained by calculating based on the relative opening of the turbine valves, the measured value of the main steam pressure, the steam generator pressure, and the primary loop heat storage coefficient.

[0152] First, obtain the relative opening of the turbine valves, the measured value of the main steam pressure, the steam generator pressure, and the primary loop heat storage coefficient of the turbine without a regulating stage.

[0153] Then, historical operating data of the nuclear power unit is obtained, including historical data such as turbine power, evaporator water level and main steam pressure. After preprocessing the historical operating data, the expression of the main steam pressure curve fitted by regression method is: f(P,W).

[0154] The energy balance signal is obtained based on the relative opening of the turbine valves and the main steam pressure curve. The energy balance signal is: G1=f(P,W)×U1;

[0155] In the formula, G1 is the energy balance signal, U1 is the relative opening of the turbine valve, f(P,W) is the function corresponding to the main steam pressure curve, P is the unit load, and W is the evaporator water level.

[0156] The heat signal is obtained based on the relative opening of the turbine valves, the measured value of the main steam pressure, the steam generator pressure, and the primary loop heat storage coefficient. The heat signal is:

[0157] In the formula, G2 is the heat signal, U1 is the relative opening degree of the turbine valve, and P T The measured value of the main steam pressure, C R P is the primary heat storage coefficient. d This refers to the steam generator pressure.

[0158] This embodiment calculates the energy balance signal and heat signal to obtain the feedforward signal. Feedforward control allows for advance adjustment of the control rod position and other parameters, reducing oscillations caused by feedback control and improving the system's dynamic adaptability. The feedforward signal enables more flexible response to grid dispatch commands, better adaptation to different operating conditions, and rapid adjustment of output power, thereby improving the overall system performance.

[0159] In some embodiments, step S400 may include, but is not limited to, the following steps:

[0160] Based on the current power measurement value of the steam turbine, the target power setting value of the steam turbine, and the power range core power of the reactor, the power mismatch response signal between the reactor and the steam turbine is obtained;

[0161] Based on the power mismatch response signal, the three-channel nonlinear control signal is determined;

[0162] The three-channel nonlinear control signal and the feedforward signal are processed by the first adder to obtain the first signal;

[0163] The control rod is positioned according to the first signal.

[0164] First, the current power measurement value of the steam turbine, the target power setting value of the steam turbine, and the nuclear power range of the reactor are obtained. The current power measurement value of the steam turbine refers to the actual output power currently measured by the steam turbine. The target power setting value of the steam turbine is obtained through logical processing based on the current power measurement value, the power grid, and the steam turbine status. The nuclear power range of the reactor refers to the measured value of the reactor's current actual nuclear power. In this embodiment, the current power measurement value of the steam turbine, the target power setting value of the steam turbine, and the nuclear power range of the reactor can all be directly obtained from the unit's DCS.

[0165] Then, based on the current power measurement of the turbine, the target power setpoint of the turbine, and the nuclear power of the reactor's power range, the power mismatch response signal between the reactor and the turbine is calculated. The power mismatch response signal is obtained by differential calculation and gain correction based on the difference between the maximum value of the current power measurement and the target power setpoint and the nuclear power of the power range. It reflects the degree of mismatch between the energy generated by the reactor and the energy required by the turbine.

[0166] Based on the power mismatch response signal, the coolant average temperature setpoint, and the coolant average temperature measurement, a three-channel nonlinear control signal is determined. The coolant average temperature measurement can be obtained through a temperature sensor, and the coolant average temperature setpoint is calculated by inputting the maximum value between the current power measurement and the target power setpoint into an average temperature setpoint function.

[0167] The three-channel nonlinear control signal and the feedforward signal are input into the first adder for synthesis to obtain a comprehensive control signal, namely the first signal. The first signal integrates information from different control channels and combines it with feedforward prediction based on energy balance, thereby providing a more comprehensive and accurate control command.

[0168] Finally, the control rods are moved up and down within the nuclear reactor by a first signal to regulate the rate of the nuclear fission reaction. Specifically, the first signal first passes through the rod speed program control unit to obtain a rod speed control signal; this rod speed control signal is then input to the control rod logic control unit to obtain a rod position control signal; finally, the rod position control signal is input to the control rod drive unit, which controls the rod position movement accordingly. Through precise control of the control rod position, the heat energy generated by the reactor can be effectively adjusted, allowing the power output of the entire unit to quickly adapt to load changes while maintaining system stability and safety.

[0169] In some embodiments, determining the three-channel nonlinear control signal based on the power mismatch response signal may include, but is not limited to, the following steps:

[0170] The maximum value between the current power measurement value and the target power setting value is determined as the first power;

[0171] The temperature corresponding to the first power is obtained according to the preset average temperature setpoint function, and the temperature corresponding to the first power is used as the coolant average temperature setpoint. The average temperature setpoint function is used to characterize the relationship between power and temperature.

[0172] The coolant average temperature setpoint, the power mismatch response signal, and the pre-acquired coolant average temperature measurement value are processed by a second adder to obtain the three-channel nonlinear control signal.

[0173] First, the maximum value between the current power measurement of the turbine and the target power setpoint is selected as the first power. Specifically, under normal operating conditions, the target power setpoint is not triggered; it is only generated under transient conditions such as turbine tripping or grid disconnection. At this point, the target power setpoint is compared with the current power measurement, and the maximum value is taken as the tracking value for reactor power and average temperature. This ensures that the control system can handle maximum power demand or actual output, thus providing sufficient margin to adjust the reactor output.

[0174] Next, the first power is input to a preset average temperature setpoint function to obtain the average coolant temperature corresponding to the first power, and this temperature value is set as the average coolant temperature setpoint. The average temperature setpoint function defines the relationship between the power level and the required average coolant temperature, and the average coolant temperature setpoint is the expected value of the coolant temperature used to ensure that the reactor operates within a safe temperature range.

[0175] Finally, the coolant average temperature setpoint, power mismatch response signal, and pre-acquired coolant average temperature measurement are input into the second adder for calculation, resulting in a three-channel nonlinear control signal. By comparing the coolant average temperature setpoint with the actual measurement value, and considering the power mismatch, a control signal is generated to guide the control rod action, thereby controlling the reactor power output.

[0176] This embodiment uses three channels of nonlinear control signals to control the coolant average temperature, power mismatch, and temperature mismatch respectively, which can effectively maintain the stability and safety of the reactor core operation, and quickly respond to changes in turbine load, thereby improving the flexibility and control effect of the nuclear power unit.

[0177] In some embodiments, obtaining the power mismatch response signal between the reactor and the turbine based on the current power measurement value of the turbine, the target power setting value of the turbine, and the nuclear power of the reactor's power range may include, but is not limited to, the following steps:

[0178] Calculate the power deviation between the first power and the core power of the power range, wherein the first power is the maximum value between the current power measurement value and the target power setting value;

[0179] The power deviation is differentiated to obtain the differential signal;

[0180] The differential signal is subjected to a nonlinear gain to obtain a gain differential signal;

[0181] The first power is subjected to a variable gain to obtain a gain power signal;

[0182] Gain correction is performed on the gain differential signal and the gain power signal to obtain the power mismatch response signal.

[0183] First, calculate the difference between the first power output and the core power output of the power range, i.e., the power deviation. The power deviation reflects the gap between the actual power generation capacity and the required or expected power generation capacity.

[0184] Secondly, the power deviation is differentiated to obtain the differential signal. The differential signal reflects the rate of change of the power deviation, that is, whether the power deviation is increasing or decreasing, and how fast it is changing.

[0185] Next, the signal undergoes gain processing. Specifically, the differential signal is processed through a nonlinear gain stage to obtain a gain differential signal. The nonlinear gain can adjust the signal strength according to the control requirements under different conditions, such as enhancing the response to rapidly changing power deviations and suppressing the effects of slowly changing power deviations. The first power signal is then processed through a variable gain stage to obtain the gain power signal. The variable gain can adjust the response strength to power deviations according to the magnitude of the first power; for example, a smaller gain can be used at low power levels to avoid excessive adjustment, while a larger gain can be used at high power levels to accelerate the response speed.

[0186] Finally, gain correction is performed on the gain derivative signal and the gain power signal to obtain the power mismatch response signal. The purpose of gain correction is to adjust the response intensity to the power deviation based on the rate of change of the power deviation and the magnitude of the initial power, so that it better meets the control requirements.

[0187] By generating a power mismatch response signal, the control rods can be guided more accurately to respond quickly to changes in turbine power, maintain power balance, and thus coordinate and optimize the operation of the nuclear power unit.

[0188] This application embodiment obtains the type of the steam turbine and the control strategy of the nuclear power unit, and calculates the corresponding energy balance signal and heat signal based on the type of the steam turbine and the control strategy of the nuclear power unit. The energy balance signal and heat signal respectively indicate the energy demand between the steam turbine and the reactor. Based on the difference between the energy balance signal and the heat signal, the feedforward model of the gap between the steam turbine energy demand and the reactor core power output can be obtained. By adding a feedforward signal to the original three-channel nonlinear control, the feedforward signal and the three-channel nonlinear control signal jointly control the rod position. The differential signal of the main steam pressure deviation can directly affect the rod position control, so that the power output of the entire unit can quickly adapt to load changes, and improve the response speed and regulation capability of the nuclear power unit when facing rapid load changes.

[0189] Referring to Figure 3, this application embodiment also provides a stacker control device 500, which can implement the above-described stacker control method. The device includes:

[0190] The acquisition module 1000 is used to acquire the type of the steam turbine and the control strategy of the nuclear power unit, wherein the nuclear power unit includes the reactor;

[0191] The first calculation module 2000 is used to calculate an energy balance signal and a heat signal according to the type of the steam turbine and the control strategy. The energy balance signal is used to indicate the minimum energy required for the steam turbine to operate, and the heat signal is used to indicate the energy produced by the reactor.

[0192] The second calculation module 3000 is used to obtain a feedforward signal based on the energy balance signal and the heat signal;

[0193] The rod position control module 4000 is used to control the rod position movement of the control rod according to the feedforward signal.

[0194] In some implementations, the rod position control module 4000 may include:

[0195] The power mismatch response signal acquisition submodule is used to obtain the power mismatch response signal between the reactor and the turbine based on the current power measurement value of the turbine, the target power setting value of the turbine, and the power range core power of the reactor.

[0196] The three-channel nonlinear control signal acquisition submodule is used to determine the three-channel nonlinear control signal based on the power mismatch response signal.

[0197] The first addition submodule is used to process the three-channel nonlinear control signal and the feedforward signal through a first adder to obtain a first signal;

[0198] The rod position control submodule is used to control the rod position movement of the control rod according to the first signal.

[0199] In some implementations, the three-channel nonlinear control signal acquisition submodule may include:

[0200] The first power acquisition unit is used to determine the maximum value between the current power measurement value and the target power setting value as the first power;

[0201] The coolant average temperature setpoint acquisition unit is used to acquire the temperature corresponding to the first power according to a preset average temperature setpoint function, and use the temperature corresponding to the first power as the coolant average temperature setpoint. The average temperature setpoint function is used to characterize the relationship between power and temperature.

[0202] The three-channel nonlinear control signal acquisition unit is used to calculate the three-channel nonlinear control signal by performing the coolant average temperature setpoint, the power mismatch response signal and the pre-acquired coolant average temperature measurement value through a second adder.

[0203] In some implementations, the power mismatch response signal acquisition submodule may include:

[0204] A power deviation calculation unit is used to calculate the power deviation between a first power and the core power of the power range, wherein the first power is the maximum value between the current power measurement value and the target power setting value;

[0205] A differential operation unit is used to perform differential operations on the power deviation to obtain a differential signal;

[0206] A nonlinear gain unit is used to perform nonlinear gain on the differential signal to obtain a gain differential signal;

[0207] A variable gain unit is used to apply a variable gain to the first power to obtain a gain power signal;

[0208] A gain correction unit is used to perform gain correction on the gain differential signal and the gain power signal to obtain the power mismatch response signal.

[0209] In some implementations, the first computing module 2000 may include:

[0210] The first acquisition submodule is used to acquire the regulating stage pressure, main steam pressure setpoint, main steam pressure measured value, steam generator pressure, and primary loop heat storage coefficient of the steam turbine with regulating stage; the type of steam turbine is a steam turbine with regulating stage, and the control strategy of the nuclear power unit is a control strategy with both main steam pressure and primary loop temperature constant.

[0211] The first energy balance signal calculation submodule is used to calculate the energy balance signal based on the regulating stage pressure, the main steam pressure setpoint, and the measured main steam pressure.

[0212] The first heat signal calculation submodule is used to calculate the heat signal based on the regulating stage pressure, the steam generator pressure, and the primary loop heat storage coefficient.

[0213] In some implementations, the first computing module 2000 may further include:

[0214] The second acquisition submodule is used to acquire the regulating stage pressure, measured main steam pressure, steam generator pressure, and primary loop heat storage coefficient of the regulating stage steam turbine; the type of the steam turbine is a regulating stage steam turbine, and the control strategy of the nuclear power unit is a control strategy with constant primary loop temperature;

[0215] The first historical operating data acquisition submodule is used to acquire historical operating data of the nuclear power unit, including turbine power, evaporator water level and main steam pressure.

[0216] The first main steam pressure curve acquisition submodule is used to obtain the main steam pressure curve based on the historical operating data. The main steam pressure curve is the curve of the main steam pressure changing with the turbine power and the evaporator water level.

[0217] The second energy balance signal calculation submodule is used to calculate the energy balance signal based on the regulating stage pressure, the main steam pressure curve, and the measured value of the main steam pressure.

[0218] The second heat signal calculation submodule is used to calculate the heat signal based on the regulating stage pressure, the steam generator pressure, and the primary loop heat storage coefficient.

[0219] In some implementations, the first computing module 2000 may further include:

[0220] The third acquisition submodule is used to acquire the relative opening of the turbine valves, the set value of the main steam pressure, the measured value of the main steam pressure, and the primary loop heat storage coefficient of the turbine without a regulating stage; the type of the turbine is a turbine without a regulating stage, and the control strategy of the nuclear power unit is a control strategy with both main steam pressure and primary loop temperature constant.

[0221] The third energy balance signal calculation submodule is used to calculate the energy balance signal based on the relative opening of the turbine valves and the main steam pressure setpoint.

[0222] The third heat signal calculation submodule is used to calculate the heat signal based on the relative opening of the turbine valves, the measured value of the main steam pressure, and the primary loop heat storage coefficient.

[0223] In some implementations, the first computing module 2000 may further include:

[0224] The fourth acquisition submodule is used to acquire the relative opening of the turbine valves, the measured value of the main steam pressure, the steam generator pressure, and the primary loop heat storage coefficient of the turbine without a regulating stage; the type of the turbine is a turbine without a regulating stage, and the control strategy of the nuclear power unit is a control strategy with constant primary loop temperature;

[0225] The second historical operating data acquisition submodule is used to acquire historical operating data of the nuclear power unit, including turbine power, evaporator water level and main steam pressure.

[0226] The second main steam pressure curve acquisition submodule is used to obtain the main steam pressure curve based on the historical operating data. The main steam pressure curve is the curve of the main steam pressure changing with the turbine power and the evaporator water level.

[0227] The fourth energy balance signal calculation submodule is used to calculate the energy balance signal based on the relative opening of the turbine valves and the main steam pressure curve.

[0228] The fourth heat signal calculation submodule is used to calculate the heat signal based on the relative opening of the turbine valves, the measured value of the main steam pressure, the steam generator pressure, and the primary loop heat storage coefficient.

[0229] The specific implementation of this stacker control device is basically the same as the specific implementation of the stacker control method described above, and will not be repeated here.

[0230] This application also provides an electronic device, which includes a memory and a processor. The memory stores a computer program, and the processor executes the computer program to implement the above-described stacker control method. This electronic device can be any smart terminal, including tablet computers, in-vehicle computers, etc.

[0231] Please refer to Figure 4, which illustrates the hardware structure of an electronic device according to another embodiment. The electronic device includes:

[0232] The processor 601 can be implemented using a general-purpose CPU (Central Processing Unit), microprocessor, application-specific integrated circuit (ASIC), or one or more integrated circuits, and is used to execute relevant programs to implement the technical solutions provided in the embodiments of this application.

[0233] The memory 602 can be implemented as a read-only memory (ROM), static storage device, dynamic storage device, or random access memory (RAM). The memory 602 can store the operating system and other application programs. When the technical solutions provided in the embodiments of this specification are implemented through software or firmware, the relevant program code is stored in the memory 602 and is called and executed by the processor 601 using the stacker control method of the embodiments of this application.

[0234] The input / output interface 603 is used to implement information input and output;

[0235] The communication interface 604 is used to enable communication and interaction between this device and other devices. Communication can be achieved through wired means (such as USB, network cable, etc.) or wireless means (such as mobile network, WIFI, Bluetooth, etc.).

[0236] Bus 605 transmits information between various components of the device (e.g., processor 601, memory 602, input / output interface 603, and communication interface 604);

[0237] The processor 601, memory 602, input / output interface 603, and communication interface 604 are connected to each other within the device via bus 605.

[0238] This application also provides a computer-readable storage medium storing a computer program that, when executed by a processor, implements the above-described stacker control method.

[0239] Memory, as a non-transitory computer-readable storage medium, can be used to store non-transitory software programs and non-transitory computer-executable programs. Furthermore, memory may include high-speed random access memory, and may also include non-transitory memory, such as at least one disk storage device, flash memory device, or other non-transitory solid-state storage device. In some embodiments, memory may optionally include memory remotely located relative to the processor, and these remote memories can be connected to the processor via a network. Examples of such networks include, but are not limited to, the Internet, intranets, local area networks, mobile communication networks, and combinations thereof.

[0240] The reactor control method, reactor control device, electronic equipment, and storage medium provided in this application calculate the corresponding feedforward signal based on the turbine type and the nuclear power unit's control strategy. This feedforward signal is combined with a three-channel nonlinear control signal to jointly control the position movement of the control rods, thereby adjusting the reactor's nuclear power and achieving coordinated control between the reactor and the turbine. By adding the corresponding feedforward control signal before rod position control, the differential signal of the main steam pressure deviation can directly affect the rod position control, effectively enhancing the rod position control capability under variable load conditions, thus improving the nuclear power unit's response speed and regulation capability.

[0241] The embodiments described in this application are for the purpose of more clearly illustrating the technical solutions of the embodiments of this application, and do not constitute a limitation on the technical solutions provided by the embodiments of this application. As those skilled in the art will know, with the evolution of technology and the emergence of new application scenarios, the technical solutions provided by the embodiments of this application are also applicable to similar technical problems.

[0242] Those skilled in the art will understand that the technical solutions shown in the figures do not constitute a limitation on the embodiments of this application, and may include more or fewer steps than shown, or combine certain steps, or different steps.

[0243] The device embodiments described above are merely illustrative. The units described as separate components may or may not be physically separate; that is, they may be located in one place or distributed across multiple network units. Some or all of the modules can be selected to achieve the purpose of this embodiment according to actual needs.

[0244] Those skilled in the art will understand that all or some of the steps in the methods disclosed above, as well as the functional modules / units in the systems and devices, can be implemented as software, firmware, hardware, or suitable combinations thereof.

[0245] The terms “first,” “second,” “third,” “fourth,” etc. (if present) in the specification and accompanying drawings of this application are used to distinguish similar objects and are not necessarily used to describe a specific order or sequence. It should be understood that such data can be interchanged where appropriate so that the embodiments of this application described herein can be implemented in orders other than those illustrated or described herein. Furthermore, the terms “comprising” and “having,” and any variations thereof, are intended to cover non-exclusive inclusion; for example, a process, method, system, product, or apparatus that comprises a series of steps or units is not necessarily limited to those steps or units explicitly listed, but may include other steps or units not explicitly listed or inherent to such processes, methods, products, or apparatus.

[0246] It should be understood that in this application, "at least one (item)" means one or more, and "more than" means two or more. "And / or" is used to describe the relationship between related objects, indicating that three relationships can exist. For example, "A and / or B" can represent three cases: only A exists, only B exists, and both A and B exist simultaneously, where A and B can be singular or plural. The character " / " generally indicates that the preceding and following related objects are in an "or" relationship. "At least one (item) of the following" or similar expressions refer to any combination of these items, including any combination of single or plural items. For example, at least one (item) of a, b, or c can represent: a, b, c, "a and b", "a and c", "b and c", or "a and b and c", where a, b, and c can be single or multiple.

[0247] In the several embodiments provided in this application, it should be understood that the disclosed apparatus and methods can be implemented in other ways. For example, the apparatus embodiments described above are merely illustrative; for instance, the division of the units described above is only a logical functional division, and in actual implementation, there may be other division methods. For example, multiple units or components may be combined or integrated into another system, or some features may be ignored or not executed. Furthermore, the coupling or direct coupling or communication connection shown or discussed may be through some interfaces; the indirect coupling or communication connection between apparatuses or units may be electrical, mechanical, or other forms.

[0248] The units described above as separate components may or may not be physically separate. The components shown as units may or may not be physical units; that is, they may be located in one place or distributed across multiple network units. Some or all of the units can be selected to achieve the purpose of this embodiment according to actual needs.

[0249] Furthermore, the functional units in the various embodiments of this application can be integrated into one processing unit, or each unit can exist physically separately, or two or more units can be integrated into one unit. The integrated unit can be implemented in hardware or as a software functional unit.

[0250] If the integrated unit is implemented as a software functional unit and sold or used as an independent product, it can be stored in a computer-readable storage medium. Based on this understanding, the technical solution of this application, in essence, or the part that contributes to the prior art, or all or part of the technical solution, can be embodied in the form of a software product. This computer software product is stored in a storage medium and includes multiple instructions to cause a computer device (which may be a personal computer, server, or network device, etc.) to execute all or part of the steps of the methods of the various embodiments of this application. The aforementioned storage medium includes various media capable of storing programs, such as USB flash drives, portable hard drives, read-only memory (ROM), random access memory (RAM), magnetic disks, or optical disks.

[0251] The preferred embodiments of the present application have been described above with reference to the accompanying drawings, but this does not limit the scope of the claims of the present application. Any modifications, equivalent substitutions, and improvements made by those skilled in the art without departing from the scope and substance of the embodiments of the present application shall be within the scope of the claims of the present application.

Claims

1. A reactor control method, the reactor comprising a reactor, a turbine, and control rods, the control rods being used to adjust the nuclear power and average temperature of the reactor, the turbine being used to convert the thermal energy generated by the reactor into mechanical energy, characterized in that, The method includes: The type of the steam turbine and the control strategy of the nuclear power unit, including the reactor, are obtained. Based on the type of steam turbine and the control strategy, an energy balance signal and a heat signal are calculated. The energy balance signal is used to indicate the minimum energy required for the steam turbine to operate, and the heat signal is used to indicate the energy produced by the reactor. The feedforward signal is obtained based on the energy balance signal and the heat signal; The position movement of the control rod is controlled according to the feedforward signal.

2. The method according to claim 1, characterized in that, The step of controlling the position movement of the control rod according to the feedforward signal includes: Based on the current power measurement value of the steam turbine, the target power setting value of the steam turbine, and the power range core power of the reactor, the power mismatch response signal between the reactor and the steam turbine is obtained; Based on the power mismatch response signal, the three-channel nonlinear control signal is determined; The three-channel nonlinear control signal and the feedforward signal are processed by the first adder to obtain the first signal; The control rod is positioned according to the first signal.

3. The method of claim 2, wherein, The step of determining the three-channel nonlinear control signal based on the power mismatch response signal includes: The maximum value between the current power measurement value and the target power setting value is determined as the first power; The temperature corresponding to the first power is obtained according to the preset average temperature setpoint function, and the temperature corresponding to the first power is used as the coolant average temperature setpoint. The average temperature setpoint function is used to characterize the relationship between power and temperature. The coolant average temperature setpoint, the power mismatch response signal, and the pre-acquired coolant average temperature measurement value are processed by a second adder to obtain the three-channel nonlinear control signal.

4. The method of claim 2, wherein, The step of obtaining the power mismatch response signal between the reactor and the turbine based on the current power measurement value of the turbine, the target power setting value of the turbine, and the power range core power of the reactor includes: Calculate the power deviation between the first power and the core power of the power range, wherein the first power is the maximum value between the current power measurement value and the target power setting value; The power deviation is differentiated to obtain the differential signal; The differential signal is subjected to a nonlinear gain to obtain a gain differential signal; The first power is subjected to a variable gain to obtain a gain power signal; Gain correction is performed on the gain differential signal and the gain power signal to obtain the power mismatch response signal.

5. The method of claim 1, wherein, The type of steam turbine is a steam turbine with a regulating stage, and the control strategy of the nuclear power unit is a control strategy with both main steam pressure and primary loop temperature being constant. The calculation of energy balance signals and heat signals based on the type of steam turbine and the control strategy of the nuclear power unit includes: The regulating stage pressure, main steam pressure setpoint, main steam pressure measured value, steam generator pressure, and primary loop heat storage coefficient of the steam turbine with regulating stage are obtained. The energy balance signal is obtained by calculating based on the regulating stage pressure, the main steam pressure setpoint, and the measured main steam pressure. The heat signal is obtained by calculating based on the regulating stage pressure, the steam generator pressure, and the primary loop heat storage coefficient.

6. The method of claim 1, wherein, The type of steam turbine is a steam turbine with a regulating stage, and the control strategy of the nuclear power unit is a control strategy with constant primary loop temperature; The calculation of energy balance signals and heat signals based on the type of steam turbine and the control strategy of the nuclear power unit includes: The measured values ​​of the regulating stage pressure, main steam pressure, steam generator pressure, and primary loop heat storage coefficient of the steam turbine with regulating stage are obtained. Acquire historical operating data of the nuclear power unit, including turbine power, evaporator water level, and main steam pressure; The main steam pressure curve is obtained based on the historical operating data. The main steam pressure curve is a curve showing the change of main steam pressure with the turbine power and the evaporator water level. The energy balance signal is obtained by calculating based on the regulating stage pressure, the main steam pressure curve, and the measured value of the main steam pressure. The heat signal is obtained by calculating based on the regulating stage pressure, the steam generator pressure, and the primary loop heat storage coefficient.

7. The method according to claim 1, characterized in that, The type of steam turbine is a steam turbine without a regulating stage, and the control strategy of the nuclear power unit is a control strategy with both main steam pressure and primary loop temperature being constant. The calculation of energy balance signals and heat signals based on the type of steam turbine and the control strategy of the nuclear power unit includes: Obtain the relative opening of the turbine valves, the set value of the main steam pressure, the measured value of the main steam pressure, and the primary loop heat storage coefficient of the turbine without a regulating stage; The energy balance signal is obtained by calculating based on the relative opening of the turbine valves and the main steam pressure setpoint. The heat signal is obtained by calculating based on the relative opening of the turbine valves, the measured value of the main steam pressure, and the primary circuit heat storage coefficient.

8. The method of claim 1, wherein, The type of steam turbine is a steam turbine without a regulating stage, and the control strategy of the nuclear power unit is a control strategy with constant primary loop temperature; The calculation of energy balance signals and heat signals based on the type of steam turbine and the control strategy of the nuclear power unit includes: Obtain the relative opening of the turbine valves, the measured value of the main steam pressure, the steam generator pressure, and the primary loop heat storage coefficient of the turbine without a regulating stage; Acquire historical operating data of the nuclear power unit, including turbine power, evaporator water level, and main steam pressure; The main steam pressure curve is obtained based on the historical operating data. The main steam pressure curve is a curve showing the change of main steam pressure with the turbine power and the evaporator water level. The energy balance signal is obtained by calculating based on the relative opening of the turbine valves and the main steam pressure curve. The heat signal is obtained by calculating based on the relative opening of the turbine valves, the measured value of the main steam pressure, the steam generator pressure, and the primary loop heat storage coefficient.

9. A stacker controller device characterized by comprising: The device includes: An acquisition module is used to acquire the type of the steam turbine and the control strategy of the nuclear power unit, wherein the nuclear power unit includes the reactor; The first calculation module is used to calculate an energy balance signal and a heat signal according to the type of the steam turbine and the control strategy. The energy balance signal is used to indicate the minimum energy required for the steam turbine to operate, and the heat signal is used to indicate the energy produced by the reactor. The second calculation module is used to obtain the feedforward signal based on the energy balance signal and the heat signal; The rod position control module is used to control the rod position movement of the control rod according to the feedforward signal.

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