Reactor power control method and apparatus, computer device and readable storage medium

Abstract

The present application relates to a reactor power control method and apparatus, a computer device and a readable storage medium. The method comprises: acquiring an initial load signal sent by a power grid; preprocessing the initial load signal to obtain an actual load signal; acquiring first feedforward information on the basis of the actual load signal and a preset load-rod position model; acquiring second feedforward information on the basis of the initial load signal, the actual load signal and a preset deviation intensity adjustment model; acquiring third feedforward information on the basis of the actual load signal and a preset amplitude limiting model; and generating a power control signal on the basis of the first feedforward information, the second feedforward information, the third feedforward information and an actual rod position value of a control rod of a reactor.

Description

Reactor power control method, device, computer equipment and readable storage medium

[0001] Related applications

[0002] This application claims priority to Chinese patent application number 2023108178798, filed on July 5, 2023, entitled “Reactor power control method, device, computer equipment and readable storage medium,” the entire text of which is hereby incorporated by reference. Technical Field

[0003] The present application relates to the field of nuclear power technology, and in particular to a reactor power control method, apparatus, computer equipment, and readable storage medium. Background Art

[0004] With the continuous optimization and adjustment of the energy mix, the participation of nuclear power units in grid frequency regulation and peak load regulation is becoming an inevitable trend. This places higher demands on the control capabilities of the nuclear power unit's Automatic Generation Control (AGC). The operational effectiveness of the AGC function is entirely dependent on the regulation quality of the nuclear power unit's coordinated control system. Nuclear power units must be able to quickly respond to power commands and quickly stabilize system parameters after power command changes to accommodate frequent power changes.

[0005] Currently, pressurized water reactor (PWR) nuclear power plants generally operate in the "reactor-follows-the-machine" mode, also known as G-mode. This mode involves the steam turbine receiving a load command signal and automatically adjusting the steam inlet to change turbine power. The reactor then adjusts its nuclear power based on changes in turbine load. In other words, under normal operating conditions, the power setpoint signal required for reactor power control is generated by the turbine's own load reference. As the load reference increases, the power setpoint also increases proportionally. While the steam turbine can respond quickly to changes in external grid commands in this mode, the reactor's passive tracking of the turbine load can easily lead to load mismatches between various circuits, exacerbating fluctuations in main steam pressure and, in severe cases, triggering the reactor protection system.

[0006] Summary of the Invention

[0007] According to various embodiments of the present application, a reactor power control method, apparatus, computer equipment, and readable storage medium are provided.

[0008] In a first aspect, the present application provides a reactor power control method, the method comprising:

[0009] Obtaining the initial load signal sent by the power grid;

[0010] Preprocessing the initial load signal to obtain an actual load signal;

[0011] Acquire first feedforward information according to the actual load signal and a preset load-rod position model;

[0012] acquiring second feedforward information according to the initial load signal, the actual load signal, and a preset deviation strength adjustment model;

[0013] Acquire third feedforward information according to the actual load signal and a preset amplitude limiting model;

[0014] A power control signal is generated according to the first feedforward information, the second feedforward information, the third feedforward information, and an actual rod position value of a control rod of the reactor.

[0015] In one embodiment, generating a power control signal according to the first feedforward information, the second feedforward information, the third feedforward information, and an actual rod position value of a control rod of the reactor includes:

[0016] calculating a rod position setting value of a control rod of the reactor according to the first feedforward information, the second feedforward information, and the third feedforward information;

[0017] The power control signal is generated according to the rod position setting value, the rod position actual value and a preset rod speed model.

[0018] In one embodiment, generating the power control signal according to the rod position set value, the rod position actual value, and a preset rod speed model includes:

[0019] Calculate the rod position deviation information according to the rod position setting value and the actual rod position value;

[0020] The rod position deviation information is processed according to a preset rod speed model to obtain the power control signal.

[0021] In one embodiment, the preprocessing of the initial load signal to obtain the actual load signal includes:

[0022] The initial load signal is rate-limited according to a preset load variation rate to obtain the actual load signal.

[0023] In one embodiment, the obtaining of first feedforward information according to the actual load signal and a preset load-rod position model includes:

[0024] inputting the actual load signal into the preset load-rod position model;

[0025] The first feedforward information corresponding to the actual load signal is obtained by matching in the preset load-rod position model.

[0026] In one embodiment, the preset deviation strength adjustment model includes a first sub-model and a second sub-model, and obtaining the second feedforward information according to the initial load signal, the actual load signal, and the preset deviation strength adjustment model includes:

[0027] Calculating reference load deviation information according to the initial load signal and the actual load signal;

[0028] Processing the reference load deviation information according to the first sub-model to obtain reference rod position feedforward information, wherein the reference rod position feedforward information is a rod position adjustment value, and the rod position adjustment value is obtained by adjusting the reference load deviation information according to a preset deviation intensity range;

[0029] The reference rod position feedforward information is subjected to preset inertia processing according to the second sub-model to obtain the second feedforward information.

[0030] In one embodiment, the obtaining of third feedforward information according to the actual load signal and a preset amplitude limiting model includes:

[0031] performing differential calculation on the actual load signal to obtain a rate of change of the actual load signal;

[0032] The amplitude of the change rate is limited according to a preset amplitude limitation model to obtain the third feedforward information.

[0033] In a second aspect, the present application further provides a reactor power control device, the device comprising:

[0034] An initial signal acquisition module is used to acquire the initial load signal sent by the power grid;

[0035] an actual signal acquisition module, configured to pre-process the initial load signal to obtain an actual load signal;

[0036] A first feedforward calculation module, configured to obtain first feedforward information according to the actual load signal and a preset load-rod position model;

[0037] a second feedforward calculation module, configured to obtain second feedforward information according to the initial load signal, the actual load signal, and a preset deviation intensity adjustment model;

[0038] a third feedforward calculation module, configured to obtain third feedforward information according to the actual load signal and a preset amplitude limiting model;

[0039] A control signal generating module is configured to generate a power control signal according to the first feedforward information, the second feedforward information, the third feedforward information, and an actual rod position value of a control rod of the reactor.

[0040] In a third aspect, the present application further provides a computer device comprising a memory and a processor, wherein the memory stores a computer program, and the processor implements the steps of the reactor power control method described in the first aspect when executing the computer program.

[0041] In a fourth aspect, the present application further provides a computer-readable storage medium having a computer program stored thereon, which, when executed by a processor, performs the steps of the reactor power control method described in the first aspect.

[0042] The details of one or more embodiments of the present application are set forth in the accompanying drawings and the description below. Other features and advantages of the present application will become apparent from the description, drawings, and claims. BRIEF DESCRIPTION OF THE DRAWINGS

[0043] In order to more clearly illustrate the embodiments of the present application or the technical solutions in the conventional technology, the following briefly introduces the drawings required for use in the embodiments or the conventional technology descriptions. Obviously, the drawings described below are merely embodiments of the present application. For ordinary technicians in this field, other drawings can be obtained based on the disclosed drawings without any creative work.

[0044] FIG1 is a schematic diagram of an application environment of a reactor power control method according to an embodiment;

[0045] FIG2 is a schematic flow chart of a reactor power control method according to an embodiment;

[0046] FIG3 is a schematic diagram of an initial load signal and an actual load signal according to an embodiment;

[0047] FIG4 is a schematic flow chart of the steps of obtaining first feedforward information according to an embodiment;

[0048] FIG5 is a schematic flow chart of the steps of obtaining second feedforward information according to an embodiment;

[0049] FIG6 is a schematic flow chart of steps for obtaining third feedforward information according to an embodiment;

[0050] FIG7 is a schematic flow chart of steps for generating a power control signal according to an embodiment;

[0051] FIG8 is a schematic flow chart of steps for generating a power control signal according to another embodiment;

[0052] FIG9 is a schematic diagram of an application scenario of a reactor power control method according to an embodiment;

[0053] FIG10 is a schematic diagram of a module of a reactor power control device according to an embodiment;

[0054] FIG11 is a diagram showing the internal structure of a computer device according to an embodiment. DETAILED DESCRIPTION

[0055] The following will be combined with the drawings in the embodiments of this application to clearly and completely describe the technical solutions in the embodiments of this application. Obviously, the embodiments described are only part of the embodiments of this application, not all of the embodiments. Based on the embodiments in this application, all other embodiments obtained by ordinary technicians in this field without making creative efforts are within the scope of protection of this application.

[0056] The reactor power control method provided in the embodiments of the present application can be applied in the application environment shown in FIG1 . Terminal 102 communicates with server 104 via a network. A data storage system can store data that server 104 needs to process. The data storage system can be integrated on server 104 or placed on a cloud or other network server. Terminal 102 can be, but is not limited to, various personal computers, laptops, smartphones, and tablet computers. Server 104 can be implemented as a standalone server or a server cluster consisting of multiple servers.

[0057] In this embodiment, the reactor power control method provided in this embodiment of the present application is applied to a pressurized water reactor (PWR) nuclear power plant, such as a PWR using a once-through steam generator (OTSG). The PWR nuclear power plant includes a reactor-machine coordinated control system. The reactor-machine coordinated control system communicates with the power grid during automatic generation control (AGC) to receive load commands from the grid.

[0058] Existing nuclear power plants using OTSGs have limited heat storage capacity and slow initial response speeds. This results in a faster response speed for large load changes, but a slower response speed for smaller load changes. If the plant meets the required response speed for small load changes, it will experience excessive load overshoot during large load changes, compromising its safety.

[0059] To address the problems of low unit load response speed and large main steam pressure fluctuations caused by low relative heat storage capacity when a pressurized water reactor nuclear power unit using an OTSG participates in AGC regulation, this embodiment proposes a reactor power control method that improves the regulation quality of the nuclear power unit coordinated control system by optimizing the power rod control feedforward link.

[0060] The following embodiments can be combined with each other, and the same or similar concepts or processes may not be repeated in some embodiments. The technical solutions in the embodiments of the present application will be clearly and completely described below in conjunction with the drawings in the embodiments of the present application. Obviously, the described embodiments are part of the embodiments of the present application, not all of the embodiments.

[0061] In one embodiment, as shown in FIG2 , a reactor power control method is provided. The method is described by taking the application environment shown in FIG1 as an example, and includes the following steps:

[0062] S201: Acquire an initial load signal sent by the power grid.

[0063] The initial load signal is a load instruction received from the power grid by the coordinated control system of the nuclear power unit. In the specific implementation process, the central dispatch office of the power grid sends the load instruction to the coordinated control system based on the actual application requirements of the nuclear power unit. This embodiment does not limit the specific parameters of the load instruction.

[0064] It should be noted that the initial load signal may also be formed by combining a given load instruction set by the unit operator for the nuclear power unit and a load instruction sent by the grid center dispatcher, which is not limited in this embodiment.

[0065] In one embodiment, the initial load signal is transmitted in the form of a step signal.

[0066] S202: Preprocess the initial load signal to obtain an actual load signal.

[0067] In one embodiment, as shown in FIG3 , since the initial load signal is transmitted in the form of a step signal, a drastic change in the initial load signal will have an impact on the nuclear power unit equipment, causing the various operating parameters of the nuclear power unit to oscillate. Therefore, after receiving the initial load signal, the coordinated control system needs to further perform a preset speed limit processing on the initial load signal to ensure the stability of the various operating parameters of the nuclear power unit.

[0068] In one embodiment, the operating parameters of the nuclear power unit include main steam pressure, average temperature of primary coolant, unit power, etc.

[0069] This embodiment can effectively avoid oscillation of various operating parameters of the nuclear power unit by performing speed limiting processing on the initial load signal, thereby protecting the parameter stability of the nuclear power unit equipment.

[0070] In one embodiment, preprocessing the initial load signal to obtain the actual load signal includes:

[0071] The initial load signal is rate-limited according to a preset load variation rate to obtain an actual load signal.

[0072] In this embodiment, a preset load change rate of 10% FP / min (FP is the rated power of the nuclear power unit) can be set to perform rate limiting processing on the initial load signal to obtain the actual load signal.

[0073] It should be noted that the preset variable load rate can be adapted to the device according to the control requirements of the actual application scenario, and this embodiment does not limit the specific value of the preset variable load rate.

[0074] S203: Acquire first feedforward information according to the actual load signal and a preset load-rod position model.

[0075] In one embodiment, when the actual load signal of the nuclear power unit is in a static state, the rod position value of the power control rod of the nuclear power unit corresponds to the actual load instruction and is in a given power control rod position.

[0076] When the actual load signal of a nuclear power plant is dynamic, the position of the power control rod of the nuclear power plant will also correspond to the dynamic changes in the actual load command, changing the power control rod position value at a certain rate so that the power of the nuclear power plant corresponds to the heat output of the steam generator. The certain rate can be set to 0-10% FP / min (where FP is the rated power of the nuclear power plant). It should be noted that the specific value of the certain rate can be adaptively adjusted according to the actual application scenario and is not specifically limited in this embodiment.

[0077] In this embodiment, a preset load-rod position model is used to match the power control rod position values ​​to the actual load signal. Specifically, the input of the preset load-rod position model is the actual load signal, and the output of the preset load-rod position model is the power control rod position value. In actual applications, the preset load-rod position model can be trained based on the results of multiple field tests. By recording the power control rod position values ​​of the nuclear power unit during stable operation under different load commands, a function model is formed that establishes a one-to-one correspondence between the actual load signal and the power control rod position value.

[0078] In one embodiment, the first feedforward information is the rod position value of the power control rod output by the load-rod position model. The first feedforward information may also be referred to as rod position static feedforward information.

[0079] This embodiment can maintain a corresponding relationship between the power of the nuclear power unit and the heat output of the steam generator by calculating the first feedforward information, thereby maintaining the stability of the operating parameters of the nuclear power unit.

[0080] S204: Acquire second feedforward information according to the initial load signal, the actual load signal, and a preset deviation strength adjustment model.

[0081] In one embodiment, due to a certain deviation between the initial load signal and the actual load signal, if there is a large disturbance in the load instruction, the rod position change of the power control rod in the existing nuclear power unit power control scheme cannot achieve the purpose of quickly increasing or decreasing the main steam pressure.

[0082] This embodiment calculates a corresponding load signal deviation based on the initial load signal and the actual load signal. This load signal deviation is then input into a preset deviation intensity adjustment model to obtain a rod position adjustment value for the power control rod that corresponds to a deviation adjustment intensity that meets the actual application scenario. In one embodiment, the power rod can be moved and adjusted based on the rod position adjustment value to change the rod position value of the power rod.

[0083] In this embodiment, the preset deviation strength adjustment model is used to make the deviation adjustment strength smaller when the load signal deviation is smaller, and to make the deviation adjustment strength larger when the load signal deviation is larger.

[0084] For example, the corresponding relationship between the load signal deviation and the rod position adjustment value in the preset deviation intensity adjustment model is shown in Table 1:

[0085] Table 1

[0086] It should be noted that in the data representing the load signal deviation in row 1 of Table 1, the specific number represents the deviation between the initial load signal and the actual load signal, and the positive or negative sign before the number indicates which of the initial and actual load signals is larger. For example, the value "-100" in row 1, column 2 indicates that the actual load signal is larger than the initial load signal, and the deviation between the two is 100MW. Similarly, in the data corresponding to the rod position adjustment value in row 2 of Table 1, the specific number represents the number of steps to be adjusted for the rod position, and the positive or negative sign before the number indicates the direction of the rod position adjustment. For example, the value "1" in row 1, column 7 indicates that the rod position is adjusted one step in the positive direction.

[0087] It can be seen from Table 1 that when the magnitude of the load signal deviation is greater than or equal to 50MW, that is, when the absolute value of the load signal deviation is greater than or equal to 50MW, the preset deviation intensity adjustment model processes the load deviation signal according to the adaptive matching deviation adjustment intensity to obtain a rod position adjustment value of 5 steps; when the magnitude of the load signal deviation is 10MW, that is, when the absolute value of the load signal deviation is 10MW, the preset deviation intensity adjustment model processes the load deviation signal according to the adaptive matching deviation adjustment intensity to obtain a rod position adjustment value of 2 steps.

[0088] In actual application, the deviation adjustment strength of the preset deviation strength adjustment model can be adaptively set according to the actual application scenario, which is not limited in this embodiment.

[0089] In one embodiment, the second feedforward information is a rod position adjustment value of the power control rod output by a preset deviation strength adjustment model. The second feedforward information may also be referred to as advance rod position feedforward information.

[0090] This embodiment can change the rod position value of the power control rod in advance by calculating the second feedforward information, so that the rod position change of the power control rod can adapt to the deviation between load instructions, thereby achieving the purpose of quickly increasing or decreasing the main steam pressure.

[0091] S205: Acquire third feedforward information according to the actual load signal and the preset amplitude limiting model.

[0092] In one embodiment, if the rate of change of the actual load signal is too large, the rod position value of the power control rod will change significantly, thereby causing the operating parameters of the nuclear power unit to oscillate.

[0093] This embodiment analyzes the dynamic changes of the actual load signal to obtain the change rate of the actual load instruction, and calculates the limited change rate of the power control rod under the dynamic changes of the actual load signal based on the change rate of the actual load instruction and a preset load limit model.

[0094] It should be noted that the third feedforward information is generated only when the actual load command changes. When the actual load command does not change, the third feedforward information is 0.

[0095] In one embodiment, the corresponding relationship between the input change rate and the output change rate in the preset amplitude limiting model is shown in Table 2:

[0096] Table 2

[0097] In one embodiment, the preset amplitude limiting model is used to limit the amplitude of the rate of change of the actual load signal.

[0098] In one embodiment, the third feedforward information is a preset amplitude limiting model output change rate. The third feedforward information may also be referred to as dynamic differential feedforward information.

[0099] S206: Generate a power control signal according to the first feedforward information, the second feedforward information, the third feedforward information, and the actual rod position value of the control rod of the reactor.

[0100] In one embodiment, the actual rod position of a nuclear power plant reactor's power control rods can be obtained using a step counter. In this embodiment, the step counter calculates the current position of the power control rod assembly inserted into the reactor core, and then processes the position through a corresponding inertia process to obtain a stable rod position. It should be noted that the time parameters of the inertia process can be adaptively set based on actual application scenarios and are not limited here.

[0101] The coordinated control system of the nuclear power unit in this embodiment calculates the corresponding rod position setting value based on the first feedforward information, the second feedforward information and the third feedforward information, and then generates a corresponding power control signal based on the deviation between the actual rod position value of the power control rod of the nuclear power unit reactor and the rod position setting value. The coordinated control system controls the power control rod to move and adjust accordingly according to the power control signal, so that the nuclear power unit outputs the corresponding power.

[0102] In summary, this embodiment provides a reactor power control method, which calculates the corresponding first feedforward information, second feedforward information and third feedforward information based on the initial load signal and the actual load signal, and then generates a power control signal for the corresponding power control rod based on the first feedforward information, the second feedforward information, the third feedforward information and the actual value of the rod position to adjust the output power of the nuclear power unit. It can adapt to large-scale and high-frequency load command changes in the power grid and keep the various operating parameters of the nuclear power unit stable.

[0103] In one embodiment, as shown in FIG4 , S203 includes:

[0104] S401: Input an actual load signal to a preset load-rod position model.

[0105] S402: Matching a preset load-rod position model to obtain first feedforward information corresponding to an actual load signal.

[0106] In one embodiment, the function of the preset load-rod position model is the same as the specific implementation of the above embodiment, which will not be repeated here.

[0107] In a specific application process, the input parameter of the preset load-rod position model is the actual load signal, and the output parameter of the preset load-rod position model is the first feedforward information, ie, the rod position static feedforward information.

[0108] In this embodiment, by configuring a specific function model for the preset load-rod position model, the power control rod position can be adjusted in real time as the actual load command changes. This ensures that the nuclear power plant reactor's output power always corresponds to the steam generator's heat output, thus ensuring the stability of the nuclear power plant's operating parameters.

[0109] Furthermore, in one embodiment, the preset deviation strength adjustment model includes a first sub-model and a second sub-model, wherein the first sub-model is used to perform deviation strength adjustment, and the second sub-model is used to perform inertia processing. As shown in FIG5 , S204 may include:

[0110] S501: Calculate reference load deviation information according to the initial load signal and the actual load signal.

[0111] S502: Process the reference load deviation information according to the first sub-model to obtain reference rod position feedforward information, where the reference rod position feedforward information is a rod position adjustment value obtained by adjusting the reference load deviation information according to a preset deviation intensity range.

[0112] S503: Perform preset inertia processing on the reference rod position feedforward information according to the second sub-model to obtain second feedforward information.

[0113] In one embodiment, a difference calculation is performed based on the initial load signal and the actual load signal to obtain reference load deviation information between the initial load signal and the actual load signal. The first sub-model is used to adjust the deviation intensity of the reference load deviation information according to a pre-set deviation intensity range to finally obtain the reference load deviation information.

[0114] The specific implementation process of the deviation strength adjustment can refer to the specific implementation methods in the aforementioned embodiments and will not be repeated here.

[0115] It should be noted that the rod position adjustment value output by the first sub-model may fluctuate frequently due to the dynamic changes in the initial load signal and the actual load signal. Therefore, for the reference rod position feedforward information output by the first sub-model, preset inertia processing must be performed according to the second sub-model to prevent the second feedforward information from fluctuating too frequently.

[0116] In one embodiment, the second sub-model includes a first-order inertia link and a second-order inertia link. In this embodiment, the reference rod position feedforward information passes through the first-order inertia link and the second-order inertia link respectively to obtain the first feedforward output information after processing by the first-order inertia link and the second feedforward output information after processing by the second-order inertia link. The first feedforward output information and the second feedforward output information together constitute the second feedforward information.

[0117] In one embodiment, the second-order inertia link may be composed of two first-order inertia links connected in series.

[0118] Among them, the first-order inertia link and the second-order inertia link are used to delay the response to the step input, filter the initial load signal, prevent frequent fluctuations in the second feedforward information, and provide the coordinated control system with rod position adjustment values ​​to compensate for the corresponding power control rods when the load is greatly disturbed.

[0119] In one embodiment, as shown in FIG6 , S205 includes:

[0120] S601: Perform differential calculation on the actual load signal to obtain the rate of change of the actual load signal.

[0121] S602: Limit the amplitude of the change rate according to a preset amplitude limiting model to obtain third feedforward information.

[0122] In one embodiment, the actual load signal is differentiated to obtain a corresponding rate of change of the actual load signal. The rate of change obtained through the differential calculation is amplitude-limited according to a preset amplitude-limiting model to obtain third feedforward information that meets the rate change requirements.

[0123] It should be noted that the specific method of differential calculation can be adaptively set according to the actual application scenario, and this embodiment does not limit this.

[0124] In one embodiment, as shown in FIG7 , S206 includes:

[0125] S701: Calculate a rod position setting value of a control rod of a reactor according to first feedforward information, second feedforward information, and third feedforward information.

[0126] S702, generating a power control signal according to the rod position setting value, the actual rod position value and the preset rod speed model.

[0127] In one embodiment, a summation operation is performed based on the first feedforward information, the second feedforward information, and the third feedforward information, and then processed by the corresponding inertia link to calculate the rod position setting value of the power control rod of the nuclear power plant reactor.

[0128] The preset rod speed model can calculate the insertion speed of the power control rod based on the difference between the rod position setting value and the actual rod position value, and the coordinated control system can generate a corresponding power control signal based on the insertion speed of the power control rod.

[0129] In this embodiment, the preset rod speed model can be trained through multiple field tests. The input of the preset rod speed model is the difference between the set rod position and the actual rod position. The output of the preset rod speed model is the insertion speed of the power control rod. This embodiment does not limit the corresponding relationship of the preset rod speed model, and it can be set based on the adaptability of the insertion speed and the difference in actual application scenarios.

[0130] In one embodiment, as shown in FIG8 , S702 includes:

[0131] S801, calculating the rod position deviation information based on the rod position setting value and the actual rod position value.

[0132] S802: Process the rod position deviation information according to a preset rod speed model to obtain a power control signal.

[0133] In one embodiment, the control rod drive module of the coordinated control system of the nuclear power unit will drive the power control rod to move a corresponding number of steps according to the corresponding insertion rod speed based on the power control signal to complete the power rod control based on the feedforward information.

[0134] In summary, the embodiments of the present application provide a reactor power control method. In the control operation of the power control rods of a nuclear power plant reactor, static rod position feedforward information, dynamic differential feedforward information, and lead rod position feedforward information adapted to the initial load signal are added. This allows the nuclear power plant to quickly generate a power control signal adapted to the changes in the initial load signal as the initial load signal changes. The power control rod position is then adjusted based on the power control signal, so that the output power of the nuclear power plant can quickly track the changing trend of the load value of the initial load signal, thereby completing rapid regulation of the reactor power. Furthermore, the reactor power control method provided in this embodiment can maintain the stability of the operating parameters of the nuclear power plant while completing rapid regulation of the reactor power, avoiding large fluctuations in the main steam pressure caused by changes in the steam turbine throttle valve opening, and effectively ensuring the operational stability of the pressurized water reactor nuclear power plant.

[0135] As shown in FIG9 , in a more detailed embodiment, when the coordinated control system of the nuclear power unit receives the initial load signal sent from the power grid, it performs rate limiting processing on the initial load signal to obtain the corresponding actual load signal; after obtaining the actual load signal, the difference between the initial load signal and the actual load signal is calculated to obtain reference load deviation information, and the reference load deviation information is processed by the first sub-model of the preset deviation strength adjustment model to obtain reference rod position feedforward information, and the reference rod position feedforward information is processed by the first-order inertia link and the second-order inertia link in the second sub-model of the preset deviation strength adjustment model to obtain corresponding second feedforward information, wherein the second-order inertia link is composed of two first-order inertia links; the actual load signal is matched with the preset load-rod position model to obtain the corresponding first feedforward information; the actual load signal is processed by differential calculation to obtain the corresponding actual load signal. The change rate of the actual load signal is then processed by a preset amplitude limit model to obtain the corresponding third feedforward information. After obtaining the first feedforward information, the second feedforward information, and the third feedforward information, the first, second, and third feedforward information are added together by an adder, and the superposition result of the adder is processed by an inertia link to calculate the corresponding rod position setting value. After the step counter collects the rod position insertion information of the power control rod, the rod position actual value is calculated by the inertia link. Finally, the difference between the rod position setting value and the rod position actual value is processed by a preset rod speed model to obtain the power control rod insertion speed required to generate the power control signal. Finally, the corresponding power control signal is generated based on the output result of the preset rod speed model and the difference between the rod position setting value and the rod position actual value. Power rod control based on the feedforward information is completed according to the power control signal.

[0136] In one embodiment, the time parameters of each inertia link (including the inertia link in the second sub-model) and the differential calculation can be adaptively set according to the needs of the actual application scenario, and this embodiment is not limited to this. In one embodiment, the time parameter of each inertia link can be set to 1, and the time constant of the differential calculation can be set to 2.

[0137] It should be understood that, although the steps in the flowcharts of the above embodiments are shown in sequence as indicated by the arrows, these steps are not necessarily performed in the order indicated by the arrows. Unless otherwise specified herein, there is no strict order restriction on the execution of these steps, and these steps can be performed in other orders. Moreover, at least a portion of the steps in the flowcharts of the above embodiments may include multiple steps or multiple stages, and these steps or stages are not necessarily performed at the same time, but can be performed at different times. The execution order of these steps or stages is not necessarily to be performed in sequence, but can be performed in turn or alternately with other steps or at least a portion of steps or stages in other steps.

[0138] Based on the same application concept, embodiments of the present application also provide a reactor power control device for implementing the aforementioned reactor power control method. The solution provided by this device is similar to the solution described in the aforementioned method. Therefore, the specific limitations of one or more reactor power control device embodiments provided below can be found in the above-described limitations of the reactor power control method and will not be further elaborated here.

[0139] In one embodiment, as shown in FIG10 , a reactor power control device 1000 is provided, comprising: an initial signal acquisition module 1010, an actual signal acquisition module 1020, a first feedforward calculation module 1030, a second feedforward calculation module 1040, a third feedforward calculation module 1050, and a control signal generation module 1060, wherein:

[0140] An initial signal acquisition module 1010 is used to acquire an initial load signal sent by the power grid;

[0141] The actual signal acquisition module 1020 is used to pre-process the initial load signal to obtain the actual load signal;

[0142] A first feedforward calculation module 1030 is configured to obtain first feedforward information based on an actual load signal and a preset load-rod position model;

[0143] A second feedforward calculation module 1040 is configured to obtain second feedforward information based on the initial load signal, the actual load signal, and a preset deviation intensity adjustment model;

[0144] A third feedforward calculation module 1050 is configured to obtain third feedforward information based on the actual load signal and a preset amplitude limiting model;

[0145] The control signal generating module 1060 is configured to generate a power control signal according to the first feedforward information, the second feedforward information, the third feedforward information, and the actual position of the control rod of the reactor.

[0146] In one embodiment, the control signal generation module 1060 is specifically configured to calculate a rod position setting value of a control rod of a reactor based on the first feedforward information, the second feedforward information, and the third feedforward information; and generate a power control signal based on the rod position setting value, the actual rod position value, and a preset rod speed model.

[0147] In one embodiment, the control signal generating module 1060 is specifically configured to calculate the rod position deviation information based on the rod position setting value and the actual rod position value; and process the rod position deviation information according to a preset rod speed model to obtain a power control signal.

[0148] In one embodiment, the actual signal acquisition module 1020 is specifically configured to perform rate limiting processing on the initial load signal according to a preset load variation rate to obtain the actual load signal.

[0149] In one embodiment, the first feedforward calculation module 1030 is specifically configured to input an actual load signal into a preset load-rod position model; and obtain first feedforward information corresponding to the actual load signal by matching the preset load-rod position model.

[0150] In one embodiment, the second feedforward calculation module 1040 is specifically used to calculate reference load deviation information based on the initial load signal and the actual load signal; process the reference load deviation information according to a preset deviation strength adjustment model to obtain reference rod position feedforward information, and the reference rod position feedforward information is the rod position value obtained after adjusting the reference load deviation information according to a preset deviation strength range; perform preset inertia processing on the reference rod position feedforward information to obtain second feedforward information.

[0151] In one embodiment, the third feedforward calculation module 1050 is specifically configured to perform differential calculation on the actual load signal to obtain the rate of change of the actual load signal; and to limit the amplitude of the rate of change according to a preset amplitude limiting model to obtain third feedforward information.

[0152] In summary, the present embodiment provides a reactor power control device that, in controlling the power control rods of a nuclear power plant reactor, adds static rod position feedforward information, dynamic differential feedforward information, and lead rod position feedforward information adapted to the initial load signal. This allows the nuclear power plant to rapidly generate a power control signal adapted to the changes in the initial load signal as the initial load signal changes. The power control rod position is then adjusted based on the power control signal, allowing the output power of the nuclear power plant to rapidly track the changing trend of the load value of the initial load signal, thereby achieving rapid regulation of the reactor power. Furthermore, the reactor power control device provided in this embodiment can maintain the stability of the operating parameters of the nuclear power plant while achieving rapid regulation of the reactor power, thereby avoiding large fluctuations in the main steam pressure caused by changes in the steam turbine throttle valve opening, and effectively ensuring the operational stability of the pressurized water reactor nuclear power plant.

[0153] Each module in the reactor power control device described above may be implemented in whole or in part through software, hardware, or a combination thereof. Each module may be embedded in or independent of a processor in a computer device in the form of hardware, or may be stored in a computer device memory in the form of software, so that the processor can call and execute the corresponding operations of each module.

[0154] In one embodiment, a computer device is provided, which may be a terminal. A diagram of its internal structure may be shown in FIG11 . The computer device includes a processor, memory, an input / output interface, a communication interface, a display unit, and an input device. The processor, memory, and input / output interface are connected via a system bus, and the communication interface, display unit, and input device are connected to the system bus via the input / output interface. The processor of the computer device is configured to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and internal memory. The non-volatile storage medium stores an operating system and a computer program. The internal memory provides an environment for the operation of the operating system and computer program in the non-volatile storage medium. The input / output interface of the computer device is configured to exchange information between the processor and an external device. The communication interface of the computer device is configured to communicate with an external terminal via wired or wireless communication, where the wireless communication may be achieved via Wi-Fi, a mobile cellular network, NFC (near-field communication), or other technologies. When executed by the processor, the computer program implements a reactor power control method. The display unit of the computer device is configured to produce a visually visible image and may be a display screen, a projection device, or a virtual reality imaging device. The display screen can be a liquid crystal display screen or an electronic ink display screen, and the input device of the computer device can be a touch layer covering the display screen, or a button, trackball or touchpad set on the computer device casing, or an external keyboard, touchpad or mouse.

[0155] Those skilled in the art will understand that the structure shown in FIG11 is merely a block diagram of a portion of the structure related to the solution of the present application, and does not constitute a limitation on the computer device to which the solution of the present application is applied. In one embodiment, the computer device may include more or fewer components than shown in the figure, or combine certain components, or have a different arrangement of components.

[0156] In one embodiment, a computer device is provided, including a memory and a processor, wherein a computer program is stored in the memory, and when the processor executes the computer program, the following steps are implemented:

[0157] Obtaining the initial load signal sent by the power grid;

[0158] Preprocessing the initial load signal to obtain the actual load signal;

[0159] Acquire first feedforward information according to the actual load signal and a preset load-rod position model;

[0160] obtaining second feedforward information according to the initial load signal, the actual load signal, and a preset deviation intensity adjustment model;

[0161] obtaining third feedforward information according to the actual load signal and the preset amplitude limiting model;

[0162] A power control signal is generated according to the first feedforward information, the second feedforward information, the third feedforward information, and an actual rod position value of a control rod of the reactor.

[0163] In one embodiment, a computer-readable storage medium is provided, on which a computer program is stored. When the computer program is executed by a processor, the following steps are implemented:

[0164] Obtaining the initial load signal sent by the power grid;

[0165] Preprocessing the initial load signal to obtain the actual load signal;

[0166] Acquire first feedforward information according to the actual load signal and a preset load-rod position model;

[0167] obtaining second feedforward information according to the initial load signal, the actual load signal, and a preset deviation intensity adjustment model;

[0168] obtaining third feedforward information according to the actual load signal and the preset amplitude limiting model;

[0169] A power control signal is generated according to the first feedforward information, the second feedforward information, the third feedforward information, and an actual rod position value of a control rod of the reactor.

[0170] Those skilled in the art will appreciate that all or part of the processes in the above-mentioned embodiment methods can be implemented by instructing the relevant hardware through a computer program, and the computer program can be stored in a non-volatile computer-readable storage medium. When the computer program is executed, it can include the processes of the embodiments of the above-mentioned methods. Among them, any reference to memory, database or other media used in the embodiments provided in this application may include at least one of non-volatile and volatile memory. Non-volatile memory may include read-only memory (ROM), magnetic tape, floppy disk, flash memory, optical memory, high-density embedded non-volatile memory, resistive random access memory (ReRAM), magnetic random access memory (MRAM), ferroelectric random access memory (FRAM), phase change memory (PCM), graphene memory, etc. Volatile memory may include random access memory (RAM) or external cache memory, etc. By way of illustration and not limitation, RAM can be in various forms, such as static random access memory (SRAM) or dynamic random access memory (DRAM). The database involved in the various embodiments provided herein may include at least one of a relational database and a non-relational database. Non-relational databases may include, but are not limited to, distributed databases based on blockchains. The processor involved in the various embodiments provided herein may be, but are not limited to, a general-purpose processor, a central processing unit, a graphics processing unit, a digital signal processor, a programmable logic unit, a data processing logic unit based on quantum computing, and the like.

[0171] The technical features of the above-mentioned embodiments can be combined arbitrarily. In order to make the description concise, not all possible combinations of the technical features in the above-mentioned embodiments are described. However, as long as there is no contradiction in the combination of these technical features, they should be considered to be within the scope of this specification.

[0172] The above-described embodiments merely represent several implementation methods of the present application. While the descriptions are relatively specific and detailed, they should not be construed as limiting the scope of the patent application. It should be noted that a person of ordinary skill in the art may make various modifications and improvements without departing from the spirit of the present application, and these modifications and improvements fall within the scope of protection of the present application. Therefore, the scope of protection of the present patent application shall be determined by the appended claims.

Claims

1. A reactor power control method, wherein: The method comprises: Obtaining the initial load signal sent by the power grid; Preprocessing the initial load signal to obtain an actual load signal; Acquire first feedforward information according to the actual load signal and a preset load-rod position model; Acquire second feedforward information according to the initial load signal, the actual load signal and a preset deviation strength adjustment model; Acquire third feedforward information according to the actual load signal and a preset amplitude limiting model; A power control signal is generated according to the first feedforward information, the second feedforward information, the third feedforward information, and an actual value of a rod position of a control rod of the reactor.

2. The method according to claim 1, wherein: The generating a power control signal according to the first feedforward information, the second feedforward information, the third feedforward information and an actual value of a rod position of a control rod of the reactor comprises: Calculate a rod position setting value of a control rod of the reactor according to the first feedforward information, the second feedforward information, and the third feedforward information; The power control signal is generated according to the rod position setting value, the rod position actual value and a preset rod speed model.

3. The method according to claim 2, wherein: The generating the power control signal according to the rod position setting value, the rod position actual value and the preset rod speed model comprises: Calculate the rod position deviation information according to the rod position setting value and the rod position actual value; The rod position deviation information is processed according to a preset rod speed model to obtain the power control signal.

4. The method according to claim 1, wherein: The preprocessing of the initial load signal to obtain an actual load signal includes: The initial load signal is rate-limited according to a preset load variation rate to obtain the actual load signal.

5. The method according to any one of claims 1 to 4, wherein: The obtaining of first feedforward information according to the actual load signal and the preset load-rod position model includes: Inputting the actual load signal into the preset load-rod position model; The first feedforward information corresponding to the actual load signal is obtained by matching in the preset load-rod position model.

6. The method according to any one of claims 1 to 4, wherein: The preset deviation strength adjustment model includes a first sub-model and a second sub-model, and the obtaining of second feedforward information according to the initial load signal, the actual load signal and the preset deviation strength adjustment model includes: Calculate reference load deviation information according to the initial load signal and the actual load signal; Processing the reference load deviation information according to the first sub-model to obtain reference rod position feedforward information, wherein the reference rod position feedforward information is a rod position adjustment value, and the rod position adjustment value is obtained by adjusting the reference load deviation information according to a preset deviation intensity range; The reference rod position feedforward information is subjected to preset inertia processing according to the second sub-model to obtain the second feedforward information.

7. The method according to any one of claims 1 to 4, wherein: The obtaining of third feedforward information according to the actual load signal and the preset amplitude limiting model includes: Performing differential calculation on the actual load signal to obtain a change rate of the actual load signal; The amplitude of the change rate is limited according to a preset amplitude limitation model to obtain the third feedforward information.

8. A reactor power control device, wherein: The device comprises: An initial signal acquisition module, used to acquire an initial load signal sent by the power grid; An actual signal acquisition module, used for preprocessing the initial load signal to obtain an actual load signal; A first feedforward calculation module, used for obtaining first feedforward information according to the actual load signal and a preset load-rod position model; A second feedforward calculation module, used for acquiring second feedforward information according to the initial load signal, the actual load signal and a preset deviation intensity adjustment model; A third feedforward calculation module, used for obtaining third feedforward information according to the actual load signal and a preset amplitude limiting model; A control signal generating module is used to generate a power control signal according to the first feedforward information, the second feedforward information, the third feedforward information and an actual value of a rod position of a control rod of the reactor.

9. A computer device comprising a memory and a processor, wherein the memory stores a computer program, wherein: When the processor executes the computer program, the steps of the reactor power control method according to any one of claims 1 to 7 are implemented.

10. A computer-readable storage medium having a computer program stored thereon, wherein: When the computer program is executed by a processor, the steps of the reactor power control method according to any one of claims 1 to 7 are implemented.

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