Stacking control method and device, electronic equipment and storage medium

Abstract

The embodiment of the invention provides a reactor control method and device, electronic equipment and a storage medium, and belongs to the technical field of nuclear power. The method comprises the steps that the type of a steam turbine and a control strategy of a nuclear power unit are obtained, and the nuclear power unit comprises a reactor; according to the type of the steam turbine and the control strategy, an energy balance signal and a heat signal are calculated, the energy balance signal is used for indicating the minimum energy needed by operation of the steam turbine, and the heat signal is used for indicating the energy generated by the reactor; obtaining a feedforward signal according to the energy balance signal and the heat signal; and controlling the rod position action of the control rod according to the feedforward signal. According to the embodiment of the invention, the response speed and the adjustment capability of the nuclear power unit in the case of rapid load change can be improved.

Description

Technical Field

[0001] The present application relates to the field of nuclear power technology, and in particular to a reactor control method, device, electronic equipment and storage medium. Background Art

[0002] At present, nuclear power units have become an indispensable part of the power supply system, especially playing a key role in providing stable and large-scale electricity. However, with the rapid development of renewable energy and the growing demand for flexible resources in the power system, the flexibility problem of nuclear power units has become increasingly apparent. Since the original intention of the design of nuclear power units is to pursue efficient and stable power output, they have insufficient regulation capabilities when dealing with the rapidly changing load demands of the power system.

[0003] The existing large-scale nuclear power units generally adopt the G-mode control method. The G-mode is a mode of reactor control for large pressurized water reactor nuclear power units, namely the "reactor follows the machine" operation mode. The steam turbine automatically adjusts the steam inlet to change the steam turbine power according to the external load command, and the reactor changes the nuclear power according to the change in the steam turbine load. Although this method is commonly used in large reactors, the reactor passively follows the change in the steam turbine load, which is easy to cause mismatch between the primary and secondary circuit loads, causing fluctuations in the main steam pressure, affecting the overall operation stability and safety of the unit. Summary of the invention

[0004] The main purpose of the embodiments of the present application is to propose a reactor control method, device, electronic device and storage medium, aiming to improve the response speed and adjustment ability of a nuclear power unit when facing rapid load changes.

[0005] To achieve the above-mentioned purpose, a first aspect of an embodiment of the present application provides a reactor control method, wherein the reactor includes a reactor, a steam turbine and a control rod, wherein the control rod is used to adjust the nuclear power of the reactor and the average temperature of the reactor, and the steam turbine is used to convert the heat energy generated by the reactor into mechanical energy, wherein the method includes:

[0006] Acquire the type of the steam turbine and the control strategy of the nuclear power unit, wherein the nuclear power unit includes the reactor;

[0007] Calculating an energy balance signal and a heat signal according to the type of the steam turbine and the control strategy, the energy balance signal being used to indicate the minimum energy required for the operation of the steam turbine, and the heat signal being used to indicate the energy generated by the reactor;

[0008] Obtaining a feedforward signal according to the energy balance signal and the heat signal;

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

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

[0011] Obtaining a power mismatch response signal between the reactor and the steam turbine according to a current power measurement value of the steam turbine, a target power setting value of the steam turbine, and a power range nuclear power of the reactor;

[0012] Determining a three-channel nonlinear control signal according to the power mismatch response signal;

[0013] Processing the three-channel nonlinear control signal and the feedforward signal through a first adder to obtain a first signal;

[0014] The rod position movement of the control rod is controlled according to the first signal.

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

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

[0017] Acquire the temperature corresponding to the first power according to a preset average temperature fixed value function, and use the temperature corresponding to the first power as the coolant average temperature setting value, wherein the average temperature fixed value function is used to characterize the relationship between power and temperature;

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

[0019] In some embodiments, obtaining a power mismatch response signal between the reactor and the steam turbine according to a current power measurement value of the steam turbine, a target power setting value of the steam turbine, and a power range nuclear power of the reactor includes:

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

[0021] Performing a differential operation on the power deviation to obtain a differential signal;

[0022] Performing nonlinear gain on the differential signal to obtain a gain differential signal;

[0023] Performing variable gain on the first power 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 type of the steam turbine is a steam turbine with a regulating stage, and the control strategy of the nuclear power unit is a dual constant control strategy of main steam pressure and primary circuit temperature;

[0026] The calculating of the energy balance signal and the heat signal according to the type of the steam turbine and the control strategy of the nuclear power unit comprises:

[0027] Obtaining the regulating stage pressure, the main steam pressure setting value, the main steam pressure measured value, the steam generator pressure and the primary circuit heat storage coefficient of the steam turbine with the regulating stage;

[0028] Calculating according to the regulating stage pressure, the main steam pressure setting value and the main steam pressure measured value to obtain the energy balance signal;

[0029] The heat signal is obtained by performing calculation according to the regulating stage pressure, the steam generator pressure and the primary circuit heat storage coefficient.

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

[0031] The calculating of the energy balance signal and the heat signal according to the type of the steam turbine and the control strategy of the nuclear power unit comprises:

[0032] Obtaining the regulating stage pressure, the measured value of the main steam pressure, the steam generator pressure and the primary circuit heat storage coefficient of the steam turbine with the regulating stage;

[0033] Acquiring historical operation data of the nuclear power unit, wherein the historical operation data includes turbine power, evaporator water level and main steam pressure;

[0034] Obtaining a main steam pressure curve according to the historical operation data, wherein the main steam pressure curve is a curve showing changes in the main steam pressure with the turbine power and the evaporator water level;

[0035] Calculating according to the regulating stage pressure, the main steam pressure curve and the measured value of the main steam pressure to obtain the energy balance signal;

[0036] The heat signal is obtained by performing calculation according to the regulating stage pressure, the steam generator pressure and the primary circuit heat storage coefficient.

[0037] In some embodiments, the type of the steam turbine is a steam turbine without a regulating stage, and the control strategy of the nuclear power unit is a dual constant control strategy of main steam pressure and primary circuit temperature;

[0038] The calculating of the energy balance signal and the heat signal according to the type of the steam turbine and the control strategy of the nuclear power unit comprises:

[0039] Obtaining the relative opening of the steam turbine valve, the main steam pressure setting value, the main steam pressure measured value and the primary circuit heat storage coefficient of the steam turbine without the regulating stage;

[0040] Calculating according to the relative opening of the steam turbine valve and the main steam pressure setting value to obtain the energy balance signal;

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

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

[0043] The calculating of the energy balance signal and the heat signal according to the type of the steam turbine and the control strategy of the nuclear power unit comprises:

[0044] Obtaining the relative opening of the steam turbine valve, the measured value of the main steam pressure, the steam generator pressure and the primary circuit heat storage coefficient of the steam turbine without the regulating stage;

[0045] Acquiring historical operation data of the nuclear power unit, wherein the historical operation data includes turbine power, evaporator water level and main steam pressure;

[0046] Obtaining a main steam pressure curve according to the historical operation data, wherein the main steam pressure curve is a curve showing changes in the main steam pressure with the turbine power and the evaporator water level;

[0047] Calculating according to the relative opening of the steam turbine valve and the main steam pressure curve to obtain the energy balance signal;

[0048] The heat signal is obtained by calculation based on the relative opening of the steam turbine valve, the measured value of the main steam pressure, the steam generator pressure and the heat storage coefficient of the first circuit.

[0049] To achieve the above-mentioned purpose, a second aspect of an embodiment of the present application provides a stacking machine control device, the device comprising:

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

[0051] A first calculation module, used for calculating an energy balance signal and a heat signal according to the type of the steam turbine and the control strategy, wherein the energy balance signal is used to indicate the minimum energy required for the operation of the steam turbine, and the heat signal is used to indicate the energy generated by the reactor;

[0052] A second calculation module, used for obtaining a feedforward signal according to the energy balance signal and the heat signal;

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

[0054] To achieve the above objectives, a third aspect of an embodiment of the present application proposes an electronic device, which includes a memory and a processor, wherein the memory stores a computer program, and when the processor executes the computer program, the method described in the first aspect is implemented.

[0055] To achieve the above-mentioned purpose, the fourth aspect of an embodiment of the present application proposes a computer-readable storage medium, wherein the computer-readable storage medium stores a computer program, and when the computer program is executed by a processor, the method described in the first aspect is implemented.

[0056] The reactor control method, device, electronic device and storage medium proposed in this application calculate the corresponding feedforward signal according to the type of steam turbine and the control strategy of the nuclear power unit, combine the feedforward signal with the three-channel nonlinear control signal, and jointly control the rod position action of the control rod, thereby adjusting the nuclear power of the reactor and realizing the coordinated control between the reactor and the steam turbine. By adding the corresponding feedforward control signal before the rod position control, the differential signal of the main steam pressure deviation can act more directly on the rod position control, effectively enhancing the rod position action control capability under variable load conditions, thereby improving the response speed and adjustment capability of the nuclear power unit. BRIEF DESCRIPTION OF THE DRAWINGS

[0057] Figure 1 It is a flow chart of a stacking machine control method provided in an embodiment of the present application;

[0058] Figure 2 It is a schematic diagram of the structural principle of a stacking machine control device provided in an embodiment of the present application;

[0059] Figure 3 is a structural schematic diagram of a stacker control device provided in an embodiment of the present application;

[0060] Figure 4 It is a schematic diagram of the hardware structure of the electronic device provided in the embodiment of the present application.

[0061] in, Figure 2The figure marks are: 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 constant channel; 121. second filter; 122. coolant average temperature constant 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 DESCRIPTION

[0062] In order to make the purpose, technical solution and advantages of the present application more clearly understood, the present application is further described in detail below in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain the present application and are not used to limit the present application.

[0063] It should be noted that, although the functional modules are divided in the device schematic diagram and the 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 above drawings are used to distinguish similar objects, and are not necessarily used to describe a specific order or sequence.

[0064] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as those commonly understood by those skilled in the art to which this application belongs. The terms used herein are only for the purpose of describing the embodiments of this application and are not intended to limit this application.

[0065] First, some nouns involved in this application are analyzed:

[0066] Primary circuit: The reactor core generates huge heat energy due to the fission of nuclear fuel. The water pumped into the core by the main pump is heated to 327 degrees and 155 atmospheres of high-temperature and high-pressure water. The high-temperature and high-pressure water flows through the heat transfer U-tube in the steam generator, and transfers the heat energy to the secondary circuit cooling water outside the U-tube through the tube wall. After releasing the heat, it is sent back to the core by the main pump for reheating and then enters the steam generator. The water circulates continuously in a closed circuit like this, which is called the primary circuit. The main function of the primary circuit is to transfer the heat generated by the nuclear reaction to the secondary circuit. The reactor coolant circulates in the primary circuit, absorbs the heat generated by the nuclear reaction, and transfers the heat to the water in the secondary circuit through the steam generator, turning it into steam.

[0067] Secondary circuit: The secondary circuit water outside the U-tube of the steam generator is heated and turned into steam, which drives the steam turbine generator to do work and converts 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 process is called the secondary circuit. The main function of the secondary circuit is to convert the heat transferred from the primary circuit into electrical energy. The steam generated by the steam generator enters the steam turbine, drives the steam turbine to rotate, and then drives the generator to generate electricity.

[0068] Power mismatch: refers to the power mismatch between the primary circuit (nuclear reactor) and the secondary circuit (steam generator). When the turbine load changes, if the reactor power regulation system cannot respond in time, it will cause a power imbalance between the primary and secondary circuits. For example, when the turbine load suddenly drops, if the reactor power regulation system cannot quickly reduce the reactor power, it will cause a reduction in the steam flow of the secondary circuit, thereby affecting the stable operation of the entire system.

[0069] Temperature mismatch: refers to the mismatch between the primary coolant temperature and the secondary steam temperature. In a nuclear power plant, the average temperature of the primary coolant needs to be kept within a stable range to ensure the safe operation of the nuclear reactor. If the steam temperature of the secondary circuit is too high or too low, it will affect the efficiency of the steam generator, and then affect the thermal efficiency and economy of the entire system. For example, when the turbine load changes, if the coolant temperature control system cannot respond in time, it will cause temperature mismatch.

[0070] 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 operations, and a combination of separate autonomy and comprehensive coordination.

[0071] Existing large nuclear power units generally adopt the G-mode control method, in which the steam turbine automatically adjusts the steam inlet to change the steam turbine power according to the external load command, and the reactor changes the nuclear power according to the change of the steam turbine load. Under this control mode, since the reactor passively responds to the change of the steam turbine load, it is easy to cause load mismatch between the primary and secondary circuits, thereby causing main steam pressure fluctuations. In addition, the core control under the G-mode is mainly composed of power mismatch and temperature mismatch, and it is impossible to directly control the main steam temperature of the pressurized water reactor with a U-type evaporator, which causes the main steam pressure to fluctuate greatly during the rapid load change process, thereby affecting the overall operation stability and safety of the unit.

[0072] Based on this, the embodiments of the present application provide a reactor control method, device, electronic device and storage medium, which aim to improve the response speed and adjustment capability of a nuclear power unit when facing rapid load changes.

[0073] The stack machine control method, device, electronic device and storage medium provided in the embodiments of the present application are specifically described through the following embodiments. First, the stack machine control method in the embodiments of the present application is described.

[0074] The reactor control method provided in the embodiment of the present application relates to the field of nuclear power technology. The reactor control method provided in the embodiment of the present application can be applied to a terminal, can be applied to a server side, or can be software running in a terminal or a server side. In some embodiments, the terminal can be a smart phone, a tablet computer, a laptop computer, a desktop computer, etc.; the server side can be configured as an independent physical server, or a server cluster or distributed system composed of multiple physical servers, or a cloud server that provides basic cloud computing services such as cloud services, cloud databases, cloud computing, cloud functions, cloud storage, network services, cloud communications, middleware services, domain name services, security services, CDN, and big data and artificial intelligence platforms; the software can be an application that implements the reactor control method, etc., but is not limited to the above forms.

[0075] The present application can be used in many general or special computer system environments or configurations. For example: 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, distributed computing environments including any of the above systems or devices, etc. The present 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. The present application can also be practiced in distributed computing environments, in which tasks are performed by remote processing devices connected through a communication network. In a distributed computing environment, program modules can be located in local and remote computer storage media including storage devices.

[0076] It should be noted that in each specific implementation of the present application, when it comes to the need to perform relevant processing based on data related to user identity or characteristics such as user information, user behavior data, user historical data, and user location information, the user's permission or consent will be obtained first, and the collection, use, and processing of these data will comply with relevant laws, regulations, and standards. In addition, when the embodiment of the present application needs to obtain the user's sensitive personal information, the user's separate permission or consent will be obtained through a pop-up window or by jumping to a confirmation page. After clearly obtaining the user's separate permission or consent, the necessary user-related data for the normal operation of the embodiment of the present application will be obtained.

[0077] Figure 1 is an optional flow chart of a reactor control method provided in an embodiment of the present application, wherein the reactor includes a reactor, a steam turbine and a control rod, wherein the control rod is used to adjust the nuclear power of the reactor and the average temperature of the reactor, and the steam turbine is used to convert the heat energy generated by the reactor into mechanical energy. Figure 1 The method may include but is not limited to steps S100 to S400.

[0078] Step S100, obtaining the type of the steam turbine and the control strategy of the nuclear power unit, wherein the nuclear power unit includes the reactor.

[0079] In this embodiment, the types of the steam turbine include steam turbines with regulating stages and steam turbines without regulating stages; the control strategies of the nuclear power unit include a control strategy of dual constant main steam pressure and primary circuit temperature and a control strategy of constant primary circuit temperature. Among them, the control strategy of dual constant main steam pressure and primary circuit temperature is a control strategy in which the main steam pressure and the average primary circuit temperature remain constant above a certain power platform (20% FP); the control strategy of constant primary circuit temperature is a control strategy in which the average primary circuit temperature remains constant and the main steam pressure changes linearly with the unit power.

[0080] Step S200, calculating an energy balance signal and a heat signal according to the type of the steam turbine and the control strategy, wherein the energy balance signal is used to indicate the minimum energy required for the operation of the steam turbine, and the heat signal is used to indicate the energy generated by the reactor.

[0081] Energy balance signal and heat signal can be obtained according to the type of steam turbine and the control strategy of nuclear power unit. The energy balance signal directly reflects the energy demand of steam turbine, while the heat signal reflects the heat generated by reactor core. The difference of energy demand between steam turbine and reactor can be obtained according to the difference of energy balance signal and heat signal.

[0082] Step S300: obtaining a feedforward signal according to the energy balance signal and the heat signal.

[0083] In this embodiment, a feedforward signal is obtained according to the energy balance signal and the heat signal, and the feedforward signal is:

[0084] G W =G1-G2;

[0085] In the formula, G W is the feedforward signal, G1 is the energy balance signal, and G2 is the heat signal. The energy balance signal and the heat signal are subtracted to obtain the feedforward signal, which is used to control the control rod.

[0086] Step S400: controlling the rod position movement of the control rod according to the feedforward signal.

[0087] The control rod is used to adjust the nuclear reaction rate. By moving the control rod up and down, the intensity of the nuclear reaction can be increased or decreased, thereby controlling the thermal power output of the reactor. The feedforward signal and the three-channel nonlinear control signal are used together in the rod speed program to drive the rod position movement of the control rod, thereby adjusting the power output of the reactor and keeping the energy balance signal consistent with the heat signal.

[0088] This embodiment adds a corresponding feedforward control signal before the rod position control. The feedforward signal directly acts on the rod position control, which can quickly adjust the insertion depth of the control rod, thereby quickly changing the reactivity of the reactor to match the energy demand of the steam turbine. Compared with traditional feedback control, the feedforward signal can predict and compensate for changes in energy demand in advance, thereby accelerating the rate of change of reactivity and improving the response speed of the unit. Introducing the feedforward signal into the control system of the nuclear power unit can effectively improve the flexibility and control capability of the nuclear power unit.

[0089] Figure 2 is an optional structural principle diagram of a stacker control device provided in an embodiment of the present application, Figure 2 The device in the control rod 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 driving unit 6.

[0090] The three-channel nonlinear control unit 1 is used to obtain a three-channel nonlinear control signal and transmit the three-channel nonlinear control signal to the first adder 3 .

[0091] The feedforward control unit 2 is used to obtain a feedforward signal and transmit the feedforward signal to the first adder 3 .

[0092] The first adder 3 is used for receiving the three-channel nonlinear control signal and the feedforward signal, obtaining the first signal according to the three-channel nonlinear control signal and the feedforward signal, and transmitting the first signal to the rod speed program control unit 4 .

[0093] The rod speed program control unit 4 is used to receive the first signal, obtain a rod speed control signal according to the first signal, and transmit the rod speed control signal to the control rod logic control unit 5 .

[0094] The control rod logic control unit 5 is used to receive a rod speed control signal, obtain a rod position control signal according to the rod speed control signal, and transmit the rod position control signal to the control rod drive unit 6 .

[0095] The control rod driving unit 6 is used to receive the rod position control signal and control the rod position movement according to the rod position control signal.

[0096] Furthermore, the three-channel nonlinear control unit 1 includes a coolant average temperature measurement channel 11 , a coolant average temperature setting channel 12 , a power mismatch channel 13 and a second adder 14 .

[0097] The coolant average temperature measurement channel 11 is used to obtain the coolant average temperature and transmit the coolant average temperature 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. Among them, the high selector 111 is used to select the maximum value of the coolant average temperature in several (usually 3) thermal loops to participate in the control. The coolant average temperature is the arithmetic mean of the temperature of the hot pipe section (nuclear reactor outlet) and the temperature of the cold pipe section (nuclear reactor inlet); the lead-lag compensator 114 is used to compensate for the response lag caused by the thermal inertia of the coolant average temperature measurement channel 11 and provide an advance signal; the first filter 113 is used to filter the thermal noise caused by the temperature sensor.

[0098] The coolant average temperature constant value channel 12 is used to obtain the coolant average temperature setting value according to the maximum value (i.e., the first power) of the current power measurement value of the steam turbine and the target power setting value of the steam turbine, and transmit the coolant average temperature setting value to the second adder 14. Specifically, the coolant average temperature constant value channel 12 includes a coolant average temperature constant value unit 122, a second filter 121, and a third filter 123. Among them, the input of the coolant average temperature constant value channel 12 is the larger value of the current power measurement value of the steam turbine and the target power setting value of the steam turbine, and then the reference value of the coolant average temperature is determined according to the larger value according to the characteristic curve preset by the coolant average temperature constant value unit 122; the second filter 121 and the third filter 123 are first-order inertial link filters.

[0099] The power mismatch channel 13 is used to obtain a power mismatch response signal according to 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 an advanced control signal to control the R rod group to accelerate the response of the nuclear reactor 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. Among them, 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 a 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 passed through 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 power range core power, and 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, and the signal after the nonlinear gain controller 134 and the signal after the variable gain controller 132 are gain-corrected in the multiplier 135, and then transmitted to the second adder 14. Due to the action of the differentiator 133, the power mismatch channel 13 provides a fast response signal according to the changing speed of the 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.

[0100] The second adder 14 is used to receive the coolant average temperature, the coolant average temperature constant and the power mismatch response signal, obtain a three-channel nonlinear control signal according to the coolant average temperature, the coolant average temperature constant and the power mismatch response signal, and transmit the three-channel nonlinear control signal to the first adder 3.

[0101] In some embodiments, step S200 may include but is not limited to the following steps:

[0102] The type of the steam turbine is a steam turbine with a regulating stage, and the control strategy of the nuclear power unit is a dual constant control strategy of main steam pressure and primary circuit temperature;

[0103] The calculating of the energy balance signal and the heat signal according to the type of the steam turbine and the control strategy of the nuclear power unit comprises:

[0104] Obtaining the regulating stage pressure, the main steam pressure setting value, the main steam pressure measured value, the steam generator pressure and the primary circuit heat storage coefficient of the steam turbine with the regulating stage;

[0105] Calculating according to the regulating stage pressure, the main steam pressure setting value and the main steam pressure measured value to obtain the energy balance signal;

[0106] The heat signal is obtained by performing calculation according to the regulating stage pressure, the steam generator pressure and the primary circuit heat storage coefficient.

[0107] According to whether the flow area of ​​the stage changes with the load, the steam turbine can be divided into a steam turbine with a regulating stage and a steam turbine without a regulating stage. Among them, the steam turbine with a regulating stage changes the amount of steam flow through an adjustable nozzle, thereby adjusting the output power of the steam turbine. The regulating stage is the first stage of the steam turbine to do work, and the load of the steam turbine can be adjusted by adjusting the flow area. The first-stage blades of the steam turbine without a regulating stage use full-circle steam inlet, and the output power mainly depends on the amount of steam entering the steam turbine, which is usually controlled by the relative opening of the steam turbine valve.

[0108] First, the regulating stage pressure, main steam pressure setting value, main steam pressure measured value, steam generator pressure and primary circuit heat storage coefficient of the steam turbine with regulating stage are obtained. Specifically, the regulating stage pressure, main steam pressure setting value, main steam pressure measured value and steam generator pressure can be directly obtained from the unit distributed control system (DCS). The primary circuit heat storage coefficient is a parameter to be determined. The steps for obtaining the primary circuit heat storage coefficient are: operate the nuclear power unit under stable conditions; release the reactor power automatic control logic, water level automatic control logic and turbine valve automatic control logic of the nuclear power unit; input a step disturbance signal to the turbine valve and record the start time of the test at the same time; record the main steam flow and main steam pressure during the test; when the unit load and main steam pressure tend to be stable, the test ends and the end time of the test is recorded; the primary circuit heat storage coefficient is obtained according to the start time of the test, the main steam flow, the main steam pressure and the end time of the test.

[0109] In some preferred embodiments, the heat storage coefficient of a circuit can be obtained according to the following formula:

[0110]

[0111] In the formula, C R is the heat storage coefficient of a circuit, t is the test time, t0 is the start time of the test, t1 is the end time of the test, D t is the main steam flow rate, P T It is the actual measured value of main steam pressure.

[0112] The energy balance signal is obtained according to the regulating stage pressure, the main steam pressure setting value and the main steam pressure measured value. The energy balance signal is:

[0113]

[0114] Where G1 is the energy balance signal, P S is the main steam pressure setting value, P1 is the regulating stage pressure, P T It is the actual measured value of main steam pressure.

[0115] A heat signal is obtained according to the regulating stage pressure, the heat storage coefficient of the first circuit and the steam generator pressure. The heat signal is:

[0116]

[0117] Where G2 is the heat signal, P d is the steam generator pressure, C R is the heat storage coefficient of a circuit.

[0118] In some embodiments, step S200 may include but is not limited to the following steps:

[0119] The type of the steam turbine is a steam turbine with a regulating stage, and the control strategy of the nuclear power unit is a control strategy of constant primary circuit temperature;

[0120] The calculating of the energy balance signal and the heat signal according to the type of the steam turbine and the control strategy of the nuclear power unit comprises:

[0121] Obtaining the regulating stage pressure, the measured value of the main steam pressure, the steam generator pressure and the primary circuit heat storage coefficient of the steam turbine with the regulating stage;

[0122] Acquiring historical operation data of the nuclear power unit, wherein the historical operation data includes turbine power, evaporator water level and main steam pressure;

[0123] Obtaining a main steam pressure curve according to the historical operation data, wherein the main steam pressure curve is a curve showing changes in the main steam pressure with the turbine power and the evaporator water level;

[0124] Calculating according to the regulating stage pressure, the main steam pressure curve and the measured value of the main steam pressure to obtain the energy balance signal;

[0125] The heat signal is obtained by performing calculation according to the regulating stage pressure, the steam generator pressure and the primary circuit heat storage coefficient.

[0126] First, the regulating stage pressure, the measured value of the main steam pressure, the steam generator pressure and the primary circuit heat storage coefficient of the steam turbine with a regulating stage are obtained.

[0127] Then, the historical operation data of the nuclear power unit is obtained, the historical operation data including historical data such as turbine power, evaporator water level and main steam pressure, and after preprocessing the historical operation data, the main steam pressure curve expression fitted by using the regression method is: f(P,W);

[0128] The energy balance signal is obtained according to the regulating stage pressure, the main steam pressure curve and the measured value of the main steam pressure. The energy balance signal is:

[0129]

[0130] Where 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, P T is the measured value of main steam pressure, P is the unit load, and W is the evaporator water level.

[0131] A heat signal is obtained according to the regulating stage pressure, the primary circuit heat storage coefficient and the steam generator pressure; the heat signal is:

[0132]

[0133] In the formula, G2 is the heat signal, Pd is the steam generator pressure, C R is the heat storage coefficient of a circuit.

[0134] In some embodiments, step S200 may include but is not limited to the following steps:

[0135] The type of the steam turbine is a steam turbine without a regulating stage, and the control strategy of the nuclear power unit is a dual constant control strategy of main steam pressure and primary circuit temperature;

[0136] The calculating of the energy balance signal and the heat signal according to the type of the steam turbine and the control strategy of the nuclear power unit comprises:

[0137] Obtaining the relative opening of the steam turbine valve, the main steam pressure setting value, the main steam pressure measured value and the primary circuit heat storage coefficient of the steam turbine without the regulating stage;

[0138] Calculating according to the relative opening of the steam turbine valve and the main steam pressure setting value to obtain the energy balance signal;

[0139] The heat signal is obtained by calculation based on the relative opening of the steam turbine valve, the measured value of the main steam pressure and the heat storage coefficient of the first circuit.

[0140] First, the relative opening of the steam turbine valve, the set value of the main steam pressure, the measured value of the main steam pressure, and the primary circuit heat storage coefficient of the steam turbine without the regulating stage are obtained. Specifically, the relative opening of the steam turbine valve, the set value of the main steam pressure, and the measured value of the main steam pressure can all be directly obtained from the unit DCS.

[0141] The energy balance signal is obtained by calculating according to the relative opening of the steam turbine valve and the main steam pressure setting value. The energy balance signal is:

[0142] G1=U1×P S ;

[0143] Where G1 is the energy balance signal, U1 is the relative opening of the turbine valve, and P S Main steam pressure setting value.

[0144] The heat signal is obtained by calculation based on the relative opening of the steam turbine valve, the measured value of the main steam pressure and the heat storage coefficient of the primary circuit. The heat signal is:

[0145]

[0146] Where G2 is the heat signal, P T is the measured value of main steam pressure, C R is the heat storage coefficient of a circuit.

[0147] In some embodiments, step S200 may include but is not limited to the following steps:

[0148] The type of the steam turbine is a steam turbine without a regulating stage, and the control strategy of the nuclear power unit is a control strategy of constant primary circuit temperature;

[0149] The calculating of the energy balance signal and the heat signal according to the type of the steam turbine and the control strategy of the nuclear power unit comprises:

[0150] Obtaining the relative opening of the steam turbine valve, the measured value of the main steam pressure, the steam generator pressure and the primary circuit heat storage coefficient of the steam turbine without the regulating stage;

[0151] Acquiring historical operation data of the nuclear power unit, wherein the historical operation data includes turbine power, evaporator water level and main steam pressure;

[0152] Obtaining a main steam pressure curve according to the historical operation data, wherein the main steam pressure curve is a curve showing changes in the main steam pressure with the turbine power and the evaporator water level;

[0153] Calculating according to the relative opening of the steam turbine valve and the main steam pressure curve to obtain the energy balance signal;

[0154] The heat signal is obtained by calculation based on the relative opening of the steam turbine valve, the measured value of the main steam pressure, the steam generator pressure and the heat storage coefficient of the first circuit.

[0155] First, the relative opening of the turbine valve, the measured value of the main steam pressure, the steam generator pressure and the primary circuit heat storage coefficient of the steam turbine without the regulating stage are obtained.

[0156] Then, the historical operation data of the nuclear power unit is obtained, the historical operation data including historical data such as turbine power, evaporator water level and main steam pressure, and after preprocessing the historical operation data, the main steam pressure curve expression fitted by using the regression method is: f(P,W);

[0157] The energy balance signal is obtained according to the relative opening of the turbine valve and the main steam pressure curve. The energy balance signal is:

[0158] G1=f(P,W)×U1;

[0159] Where 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.

[0160] The heat signal is obtained according to the relative opening of the turbine valve, the measured value of the main steam pressure, the steam generator pressure and the heat storage coefficient of the primary circuit. The heat signal is:

[0161]

[0162] Where G2 is the heat signal, U1 is the relative opening of the turbine valve, and P T is the measured value of main steam pressure, C R is the heat storage coefficient of a circuit, P d is the steam generator pressure.

[0163] This embodiment calculates the energy balance signal and the heat signal to obtain the feedforward signal. Through feedforward control, the position and other parameters of the control rod can be adjusted in advance to reduce the oscillation caused by feedback control, thereby improving the dynamic adaptability of the system. Through the feedforward signal, it is possible to respond to the grid dispatching command more flexibly, better adapt to different operating conditions, and quickly adjust the output power, thereby improving the overall performance of the system.

[0164] In some embodiments, step S400 may include but is not limited to the following steps:

[0165] Obtaining a power mismatch response signal between the reactor and the steam turbine according to a current power measurement value of the steam turbine, a target power setting value of the steam turbine, and a power range nuclear power of the reactor;

[0166] Determining a three-channel nonlinear control signal according to the power mismatch response signal;

[0167] Processing the three-channel nonlinear control signal and the feedforward signal through a first adder to obtain a first signal;

[0168] The rod position movement of the control rod is controlled according to the first signal.

[0169] First, obtain the current power measurement value of the steam turbine, the target power setting value of the steam turbine, and the power range nuclear power of the reactor. Among them, 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 a setting value obtained through logical processing based on the current power measurement value, the power grid and the steam turbine status, and the power range nuclear power of the reactor refers to the measurement value of the current actual nuclear power of the reactor. In this embodiment, the current power measurement value of the steam turbine, the target power setting value of the steam turbine, and the power range nuclear power of the reactor can all be directly obtained from the unit DCS.

[0170] Then, the power mismatch response signal between the reactor and the steam turbine is calculated based on the current power measurement value of the steam turbine, the target power setting value of the steam turbine and the power range nuclear power of the reactor. The power mismatch response signal is obtained by differential operation and gain correction based on the difference between the maximum value of the current power measurement value and the target power setting value and the power range nuclear power, reflecting the mismatch between the energy generated by the reactor and the energy required by the steam turbine.

[0171] Based on the power mismatch response signal, the coolant average temperature setting value and the coolant average temperature measurement value, a three-channel nonlinear control signal is determined. The coolant average temperature measurement value can be measured by a temperature sensor, and the coolant average temperature setting value is calculated by inputting the maximum value of the current power measurement value and the target power setting value into the average temperature setting function.

[0172] 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 feedforward prediction based on energy balance, thereby providing a more comprehensive and accurate control instruction.

[0173] Finally, the first signal drives the control rod to move up and down in the nuclear reactor to adjust the speed 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; the rod speed control signal is input into the control rod logic control unit to obtain a rod position control signal; the rod position control signal is then input into the control rod drive unit to control the rod position according to the rod position control signal. By accurately controlling the position of the control rod, the heat energy generated by the reactor can be effectively adjusted so that the power output of the entire unit can quickly adapt to load changes while maintaining the stability and safety of the system.

[0174] In some embodiments, determining the three-channel nonlinear control signal according to the power mismatch response signal may include, but is not limited to, the following steps:

[0175] Determine the maximum value between the current power measurement value and the target power setting value as the first power;

[0176] Acquire the temperature corresponding to the first power according to a preset average temperature fixed value function, and use the temperature corresponding to the first power as the coolant average temperature setting value, wherein the average temperature fixed value function is used to characterize the relationship between power and temperature;

[0177] The coolant average temperature setting value, the power mismatch response signal and the pre-acquired coolant average temperature measurement value are operated through a second adder to obtain the three-channel nonlinear control signal.

[0178] First, the maximum value is selected from the current power measurement value and the target power setting value of the steam turbine as the first power. Specifically, under normal operating conditions, the target power setting value will not be triggered. The target power setting value will only be generated when transient conditions such as turbine tripping or grid disconnection occur. Only then will the target power setting value be compared with the current power measurement value, and the maximum value will be taken as the tracking value of the reactor power and average temperature to ensure that the control system can cope with the maximum power demand or actual output, thereby providing sufficient space to adjust the output of the reactor.

[0179] Secondly, the first power is input into a preset average temperature setting function to obtain the average coolant temperature corresponding to the first power, and this temperature value is set as the coolant average temperature setting value. The average temperature setting function defines the relationship between the power level and the required coolant average temperature, and the coolant average temperature setting value is the expected value of the coolant temperature to ensure that the reactor operates within a safe temperature range.

[0180] Finally, the coolant average temperature setting value, the power mismatch response signal and the pre-acquired coolant average temperature measurement value are input into the second adder for operation to obtain a three-channel nonlinear control signal. By comparing the coolant average temperature setting value and the actual measurement value, and considering the power mismatch, a control signal for guiding the control rod action is generated to control the reactor power output.

[0181] This embodiment controls the coolant average temperature, power mismatch and temperature mismatch respectively through three-channel nonlinear control signals, which can effectively maintain the stability and safety of core operation, quickly respond to changes in turbine load, and improve the flexibility and control effect of nuclear power units.

[0182] In some embodiments, obtaining a power mismatch response signal between the reactor and the steam turbine according to the current power measurement value of the steam turbine, the target power setting value of the steam turbine and the power range nuclear power of the reactor may include but is not limited to the following steps:

[0183] Calculating a power deviation between a first power and the power range core power, wherein the first power is a maximum value between the current power measurement value and the target power setting value;

[0184] Performing a differential operation on the power deviation to obtain a differential signal;

[0185] Performing nonlinear gain on the differential signal to obtain a gain differential signal;

[0186] Performing variable gain on the first power to obtain a gain power signal;

[0187] Gain correction is performed on the gain differential signal and the gain power signal to obtain the power mismatch response signal.

[0188] First, the difference between the first power and the power range core power, namely the power deviation, is calculated. The power deviation reflects the gap between the actual power generation capacity and the required or expected power generation capacity.

[0189] Secondly, the power deviation is differentiated to obtain a differential signal, which reflects the speed of change of the power deviation, that is, whether the power deviation increases or decreases, and how fast it changes.

[0190] Then, the signal is subjected to gain processing. Specifically, the differential signal is processed through a nonlinear gain link to obtain a gain differential signal. The nonlinear gain can adjust the signal strength according to the control requirements in different situations, such as enhancing the response to rapidly changing power deviations and suppressing the influence of slowly changing power deviations. The first power is processed through a variable gain link to obtain a gain power signal. The variable gain can adjust the response strength to the power deviation according to the size of the first power, such as using a smaller gain at a low power level to avoid excessive adjustment action, and using a larger gain at a high power level to speed up the response speed.

[0191] Finally, the gain differential signal and the gain power signal are subjected to gain correction to obtain a power mismatch response signal. The function of the gain correction is to adjust the response intensity to the power deviation according to the change speed of the power deviation and the magnitude of the first power, so as to make it more in line with the control requirements.

[0192] By generating a power mismatch response signal, the action of the control rods can be guided more accurately, the turbine power changes can be responded to quickly, the power balance can be maintained, and the operation of the nuclear power unit can be coordinated and optimized.

[0193] The embodiment of the present application 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 according to the type of the steam turbine and the control strategy of the nuclear power unit, the energy balance signal and the heat signal respectively indicating the energy demand between the steam turbine and the reactor; according to the difference between the energy balance signal and the heat signal, a feedforward model of the difference between the energy demand of the steam turbine and the power output of the reactor core can be obtained; on the basis of the original three-channel nonlinear control, a feedforward signal is added, so that the feedforward signal and the three-channel nonlinear control signal jointly control the rod position, and the differential signal of the main steam pressure deviation can act more directly on the rod position control, so that the power output of the entire unit can quickly adapt to load changes, thereby improving the response speed and adjustment ability of the nuclear power unit when facing rapid load changes.

[0194] See also Figure 3 The embodiment of the present application further provides a stacker control device 500, which can implement the above stacker control method, and the device includes:

[0195] An 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;

[0196] A first calculation module 2000, for calculating an energy balance signal and a heat signal according to the type of the steam turbine and the control strategy, wherein the energy balance signal is used to indicate the minimum energy required for the operation of the steam turbine, and the heat signal is used to indicate the energy generated by the reactor;

[0197] A second calculation module 3000, configured to obtain a feedforward signal according to the energy balance signal and the heat signal;

[0198] The rod position control module 4000 is used to control the rod position movement of the control rod according to the feedforward signal.

[0199] In some embodiments, the stick position control module 4000 may include:

[0200] A power mismatch response signal acquisition submodule, used to obtain a power mismatch response signal between the reactor and the steam turbine according to a current power measurement value of the steam turbine, a target power setting value of the steam turbine and a power range nuclear power of the reactor;

[0201] A three-channel nonlinear control signal acquisition submodule, used to determine a three-channel nonlinear control signal according to the power mismatch response signal;

[0202] A first adding submodule, used for processing the three-channel nonlinear control signal and the feedforward signal through a first adder to obtain a first signal;

[0203] The rod position control submodule is used to control the rod position movement of the control rod according to the first signal.

[0204] In some embodiments, the three-channel nonlinear control signal acquisition submodule may include:

[0205] A first power acquisition unit, configured to determine a maximum value between the current power measurement value and the target power setting value as a first power;

[0206] a coolant average temperature setting value acquisition unit, used to acquire the temperature corresponding to the first power according to a preset average temperature fixed value function, and use the temperature corresponding to the first power as the coolant average temperature setting value, wherein the average temperature fixed value function is used to characterize the relationship between power and temperature;

[0207] The three-channel nonlinear control signal acquisition unit is used to calculate the coolant average temperature setting value, the power mismatch response signal and the pre-acquired coolant average temperature measurement value through a second adder to obtain the three-channel nonlinear control signal.

[0208] In some implementations, the power mismatch response signal acquisition submodule may include:

[0209] A power deviation calculation unit, used for calculating a power deviation between a first power and the power range core power, wherein the first power is a maximum value between the current power measurement value and the target power setting value;

[0210] A differential operation unit, used for performing a differential operation on the power deviation to obtain a differential signal;

[0211] A nonlinear gain unit, used for performing nonlinear gain on the differential signal to obtain a gain differential signal;

[0212] A variable gain unit, used for performing variable gain on the first power to obtain a gain power signal;

[0213] 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.

[0214] In some implementations, the first computing module 2000 may include:

[0215] The first acquisition submodule is used to obtain the regulating stage pressure, the main steam pressure setting value, the main steam pressure measured value, the steam generator pressure and the primary circuit heat storage coefficient of the steam turbine with a regulating stage; the type of the steam turbine is a steam turbine with a regulating stage, and the control strategy of the nuclear power unit is a dual constant control strategy of the main steam pressure and the primary circuit temperature;

[0216] A first energy balance signal calculation submodule, configured to calculate according to the regulating stage pressure, the main steam pressure setting value and the main steam pressure measured value to obtain the energy balance signal;

[0217] The first heat signal calculation submodule is used to calculate according to the regulating stage pressure, the steam generator pressure and the primary circuit heat storage coefficient to obtain the heat signal.

[0218] In some implementations, the first calculation module 2000 may further include:

[0219] The second acquisition submodule is used to obtain the regulating stage pressure, the measured value of the main steam pressure, the steam generator pressure and the primary circuit heat storage coefficient of the steam turbine with a regulating stage; the type of the steam turbine is a steam turbine with a regulating stage, and the control strategy of the nuclear power unit is a control strategy of constant primary circuit temperature;

[0220] A first historical operation data acquisition submodule is used to acquire historical operation data of the nuclear power unit, wherein the historical operation data includes turbine power, evaporator water level and main steam pressure;

[0221] A first main steam pressure curve acquisition submodule, used to obtain a main steam pressure curve according to the historical operation data, wherein the main steam pressure curve is a curve showing the main steam pressure changes with the turbine power and the evaporator water level;

[0222] A second energy balance signal calculation submodule, configured to calculate according to the regulating stage pressure, the main steam pressure curve and the measured value of the main steam pressure to obtain the energy balance signal;

[0223] The second heat signal calculation submodule is used to calculate according to the regulating stage pressure, the steam generator pressure and the primary circuit heat storage coefficient to obtain the heat signal.

[0224] In some implementations, the first calculation module 2000 may further include:

[0225] The third acquisition submodule is used to obtain the relative opening of the steam turbine valve, the main steam pressure setting value, the main steam pressure measured value and the primary circuit heat storage coefficient of the steam turbine without a regulating stage; the type of the steam turbine is a steam turbine without a regulating stage, and the control strategy of the nuclear power unit is a control strategy of dual constant main steam pressure and primary circuit temperature;

[0226] A third energy balance signal calculation submodule, configured to calculate according to the relative opening of the steam turbine valve and the main steam pressure setting value to obtain the energy balance signal;

[0227] The third heat signal calculation submodule is used to calculate according to the relative opening of the turbine valve, the measured value of the main steam pressure and the heat storage coefficient of the first circuit to obtain the heat signal.

[0228] In some implementations, the first calculation module 2000 may further include:

[0229] The fourth acquisition submodule is used to obtain the relative opening of the steam turbine valve, the measured value of the main steam pressure, the steam generator pressure and the primary circuit heat storage coefficient of the steam turbine without the regulating stage; the type of the steam turbine is a steam turbine without the regulating stage, and the control strategy of the nuclear power unit is a control strategy of constant primary circuit temperature;

[0230] A second historical operation data acquisition submodule is used to acquire historical operation data of the nuclear power unit, wherein the historical operation data includes turbine power, evaporator water level and main steam pressure;

[0231] A second main steam pressure curve acquisition submodule is used to obtain a main steam pressure curve according to the historical operation data, wherein the main steam pressure curve is a curve showing the main steam pressure changes with the turbine power and the evaporator water level;

[0232] a fourth energy balance signal calculation submodule, configured to calculate according to the relative opening of the steam turbine valve and the main steam pressure curve to obtain the energy balance signal;

[0233] The fourth heat signal calculation submodule is used to calculate according to the relative opening of the turbine valve, the measured value of the main steam pressure, the steam generator pressure and the heat storage coefficient of the first circuit to obtain the heat signal.

[0234] The specific implementation of the stacker control device is basically the same as the specific implementation of the stacker control method described above, and will not be repeated here.

[0235] The embodiment of the present application also provides an electronic device, the electronic device includes a memory and a processor, the memory stores a computer program, and the processor implements the above stacker control method when executing the computer program. The electronic device can be any intelligent terminal including a tablet computer, a vehicle-mounted computer, etc.

[0236] See also Figure 4 , Figure 4 The hardware structure of an electronic device of another embodiment is illustrated, and the electronic device includes:

[0237] The processor 601 may be implemented by a general-purpose CPU (Central Processing Unit), a microprocessor, an 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 the present application;

[0238] The memory 602 can be implemented in the form of a read-only memory (ROM), a static storage device, a dynamic storage device, or a random access memory (RAM). The memory 602 can store an operating system and other application programs. When the technical solution provided in the embodiment of this specification is implemented by software or firmware, the relevant program code is stored in the memory 602, and the processor 601 calls and executes the stack machine control method of the embodiment of this application;

[0239] Input / output interface 603, used to implement information input and output;

[0240] Communication interface 604, used to realize communication interaction between the device and other devices, which can be realized through wired mode (such as USB, network cable, etc.) or wireless mode (such as mobile network, WI FI, Bluetooth, etc.);

[0241] Bus 605 , which transmits information between various components of the device (e.g., processor 601 , memory 602 , input / output interface 603 , and communication interface 604 );

[0242] The processor 601 , the memory 602 , the input / output interface 603 and the communication interface 604 are connected to each other in communication within the device via a bus 605 .

[0243] An embodiment of the present application further provides a computer-readable storage medium, which stores a computer program. When the computer program is executed by a processor, the above-mentioned stack machine control method is implemented.

[0244] The memory, as a non-transient computer-readable storage medium, can be used to store non-transient software programs and non-transient computer executable programs. In addition, the memory may include a high-speed random access memory, and may also include a non-transient memory, such as at least one disk storage device, a flash memory device, or other non-transient solid-state storage device. In some embodiments, the memory may optionally include a memory remotely disposed relative to the processor, and these remote memories may be connected to the processor via a network. Examples of the above-mentioned network include, but are not limited to, the Internet, an intranet, a local area network, a mobile communication network, and combinations thereof.

[0245] The reactor control method, reactor control device, electronic device and storage medium provided in the embodiment of the present application calculate the corresponding feedforward signal according to the type of steam turbine and the control strategy of the nuclear power unit, combine the feedforward signal with the three-channel nonlinear control signal, and jointly control the rod position action of the control rod, thereby adjusting the nuclear power of the reactor and realizing the coordinated control between the reactor and the steam turbine. By adding the corresponding feedforward control signal before the rod position control, the differential signal of the main steam pressure deviation can act more directly on the rod position control, effectively enhancing the rod position action control capability under variable load conditions, thereby improving the response speed and adjustment capability of the nuclear power unit.

[0246] The embodiments described in the embodiments of the present application are intended to more clearly illustrate the technical solutions of the embodiments of the present application and do not constitute a limitation on the technical solutions provided in the embodiments of the present application. Those skilled in the art will appreciate that with the evolution of technology and the emergence of new application scenarios, the technical solutions provided in the embodiments of the present application are also applicable to similar technical problems.

[0247] Those skilled in the art will appreciate that the technical solutions shown in the figures do not constitute a limitation on the embodiments of the present application, and may include more or fewer steps than shown in the figures, or a combination of certain steps, or different steps.

[0248] The device embodiments described above are merely illustrative, and the units described as separate components may or may not be physically separated, that is, they may be located in one place or distributed on multiple network units. Some or all of the modules may be selected according to actual needs to achieve the purpose of the solution of this embodiment.

[0249] Those skilled in the art will appreciate that all or some of the steps in the methods disclosed above, and the functional modules / units in the systems and devices may be implemented as software, firmware, hardware, or a suitable combination thereof.

[0250] The terms "first", "second", "third", "fourth", etc. (if any) in the specification of the present application and the above-mentioned drawings are used to distinguish similar objects, and are not necessarily used to describe a specific order or sequence. It should be understood that the data used in this way can be interchangeable where appropriate, so that the embodiments of the present application described herein can be implemented in an order other than those illustrated or described herein. In addition, the terms "including" and "having" and any of their variations are intended to cover non-exclusive inclusions, for example, a process, method, system, product or device comprising a series of steps or units is not necessarily limited to those steps or units clearly listed, but may include other steps or units that are not clearly listed or inherent to these processes, methods, products or devices.

[0251] It should be understood that in the present application, "at least one (item)" means one or more, and "plurality" means two or more. "And / or" is used to describe the association relationship of associated objects, indicating that three relationships may exist. For example, "A and / or B" can mean: only A exists, only B exists, and A and B exist at the same time, where A and B can be singular or plural. The character " / " generally indicates that the objects associated before and after are in an "or" relationship. "At least one of the following" or similar expressions refers to any combination of these items, including any combination of single or plural items. For example, at least one of a, b or c can mean: a, b, c, "a and b", "a and c", "b and c", or "a and b and c", where a, b, c can be single or multiple.

[0252] In the several embodiments provided in the present application, it should be understood that the disclosed devices and methods can be implemented in other ways. For example, the device embodiments described above are only schematic. For example, the division of the above units is only a logical function division. There may be other division methods in actual implementation, such as multiple units or components can be combined or integrated into another system, or some features can be ignored or not executed. Another point is that the mutual coupling or direct coupling or communication connection shown or discussed can be through some interfaces, indirect coupling or communication connection of devices or units, which can be electrical, mechanical or other forms.

[0253] The units described above as separate components may or may not be physically separated, and the components shown as units may or may not be physical units, that is, they may be located in one place or distributed on multiple network units. Some or all of the units may be selected according to actual needs to achieve the purpose of the solution of this embodiment.

[0254] In addition, each functional unit in each embodiment of the present application may be integrated into one processing unit, or each unit may exist physically separately, or two or more units may be integrated into one unit. The above-mentioned integrated unit may be implemented in the form of hardware or in the form of software functional units.

[0255] If the integrated unit is implemented in the form of 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 the present application is essentially 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, and the computer software product is stored in a storage medium, including multiple instructions to enable a computer device (which can be a personal computer, server, or network device, etc.) to execute all or part of the steps of the methods of various embodiments of the present application. The aforementioned storage medium includes: U disk, mobile hard disk, read-only memory (Read-Only Memory, referred to as ROM), random access memory (Random Access Memory, referred to as RAM), disk or optical disk and other media that can store programs.

[0256] The preferred embodiments of the present invention are described above with reference to the accompanying drawings, but the scope of the rights of the present invention is not limited thereto. Any modification, equivalent substitution and improvement made by a person skilled in the art without departing from the scope and essence of the present invention should be within the scope of the rights of the present invention.

Claims

1. A method for controlling a reactor machine, the reactor machine comprising a reactor, a steam turbine and a control rod, the control rod being used to adjust the nuclear power of the reactor and the average temperature of the reactor, the steam turbine being used to convert the heat energy generated by the reactor into mechanical energy, characterized in that: The method comprises: Acquire the type of the steam turbine and the control strategy of the nuclear power unit, wherein the nuclear power unit includes the reactor; Calculating an energy balance signal and a heat signal according to the type of the steam turbine and the control strategy, the energy balance signal being used to indicate the minimum energy required for the operation of the steam turbine, and the heat signal being used to indicate the energy generated by the reactor; Obtaining a feedforward signal according to the energy balance signal and the heat signal; The rod 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 rod position movement of the control rod according to the feedforward signal comprises: Obtaining a power mismatch response signal between the reactor and the steam turbine according to a current power measurement value of the steam turbine, a target power setting value of the steam turbine, and a power range nuclear power of the reactor; Determining a three-channel nonlinear control signal according to the power mismatch response signal; Processing the three-channel nonlinear control signal and the feedforward signal through a first adder to obtain a first signal; The rod position movement of the control rod is controlled according to the first signal.

3. The method according to claim 2, characterized in that Determining the three-channel nonlinear control signal according to the power mismatch response signal includes: Determine the maximum value between the current power measurement value and the target power setting value as the first power; Acquire the temperature corresponding to the first power according to a preset average temperature fixed value function, and use the temperature corresponding to the first power as the coolant average temperature setting value, wherein the average temperature fixed value function is used to characterize the relationship between power and temperature; The coolant average temperature setting value, the power mismatch response signal and the pre-acquired coolant average temperature measurement value are operated through a second adder to obtain the three-channel nonlinear control signal.

4. The method according to claim 2, characterized in that: The step of obtaining a power mismatch response signal between the reactor and the steam turbine according to the current power measurement value of the steam turbine, the target power setting value of the steam turbine and the power range nuclear power of the reactor comprises: Calculating a power deviation between a first power and the power range core power, wherein the first power is a maximum value between the current power measurement value and the target power setting value; Performing a differential operation on the power deviation to obtain a differential signal; Performing nonlinear gain on the differential signal to obtain a gain differential signal; Performing variable gain on the first power 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 according to claim 1, characterized in that The type of the steam turbine is a steam turbine with a regulating stage, and the control strategy of the nuclear power unit is a dual constant control strategy of main steam pressure and primary circuit temperature; The calculating of the energy balance signal and the heat signal according to the type of the steam turbine and the control strategy of the nuclear power unit comprises: Obtaining the regulating stage pressure, the main steam pressure setting value, the main steam pressure measured value, the steam generator pressure and the primary circuit heat storage coefficient of the steam turbine with the regulating stage; Calculating according to the regulating stage pressure, the main steam pressure setting value and the main steam pressure measured value to obtain the energy balance signal; The heat signal is obtained by performing calculation according to the regulating stage pressure, the steam generator pressure and the primary circuit heat storage coefficient.

6. The method according to claim 1, characterized in that The type of the steam turbine is a steam turbine with a regulating stage, and the control strategy of the nuclear power unit is a control strategy of constant primary circuit temperature; The calculating of the energy balance signal and the heat signal according to the type of the steam turbine and the control strategy of the nuclear power unit comprises: Obtaining the regulating stage pressure, the measured value of the main steam pressure, the steam generator pressure and the primary circuit heat storage coefficient of the steam turbine with the regulating stage; Acquiring historical operation data of the nuclear power unit, wherein the historical operation data includes turbine power, evaporator water level and main steam pressure; Obtaining a main steam pressure curve according to the historical operation data, wherein the main steam pressure curve is a curve showing changes in the main steam pressure with the turbine power and the evaporator water level; Calculating according to the regulating stage pressure, the main steam pressure curve and the measured value of the main steam pressure to obtain the energy balance signal; The heat signal is obtained by performing calculation according to the regulating stage pressure, the steam generator pressure and the primary circuit heat storage coefficient.

7. The method according to claim 1, characterized in that The type of the steam turbine is a steam turbine without a regulating stage, and the control strategy of the nuclear power unit is a dual constant control strategy of main steam pressure and primary circuit temperature; The calculating of the energy balance signal and the heat signal according to the type of the steam turbine and the control strategy of the nuclear power unit comprises: Obtaining the relative opening of the steam turbine valve, the main steam pressure setting value, the main steam pressure measured value and the primary circuit heat storage coefficient of the steam turbine without the regulating stage; Calculating according to the relative opening of the steam turbine valve and the main steam pressure setting value to obtain the energy balance signal; The heat signal is obtained by calculation based on the relative opening of the steam turbine valve, the measured value of the main steam pressure and the heat storage coefficient of the first circuit.

8. The method according to claim 1, characterized in that The type of the steam turbine is a steam turbine without a regulating stage, and the control strategy of the nuclear power unit is a control strategy of constant primary circuit temperature; The calculating of the energy balance signal and the heat signal according to the type of the steam turbine and the control strategy of the nuclear power unit comprises: Obtaining the relative opening of the steam turbine valve, the measured value of the main steam pressure, the steam generator pressure and the primary circuit heat storage coefficient of the steam turbine without the regulating stage; Acquiring historical operation data of the nuclear power unit, wherein the historical operation data includes turbine power, evaporator water level and main steam pressure; Obtaining a main steam pressure curve according to the historical operation data, wherein the main steam pressure curve is a curve showing changes in the main steam pressure with the turbine power and the evaporator water level; Calculating according to the relative opening of the steam turbine valve and the main steam pressure curve to obtain the energy balance signal; The heat signal is obtained by calculation based on the relative opening of the steam turbine valve, the measured value of the main steam pressure, the steam generator pressure and the heat storage coefficient of the first circuit.

9. A stacker control device, characterized in that: The device comprises: An acquisition module, used for acquiring the type of the steam turbine and the control strategy of the nuclear power unit, wherein the nuclear power unit includes the reactor; A first calculation module, used for calculating an energy balance signal and a heat signal according to the type of the steam turbine and the control strategy, wherein the energy balance signal is used to indicate the minimum energy required for the operation of the steam turbine, and the heat signal is used to indicate the energy generated by the reactor; A second calculation module, used for obtaining a feedforward signal according to the energy balance signal and the heat signal; A rod position control module is used to control the rod position movement of the control rod according to the feedforward signal.

10. An electronic device, characterized in that: The electronic device includes a memory and a processor, the memory stores a computer program, and the processor implements the stack machine control method according to any one of claims 1 to 8 when executing the computer program.

11. A computer-readable storage medium storing a computer program, characterized in that: When the computer program is executed by a processor, the stack machine control method according to any one of claims 1 to 8 is implemented.

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