Method and system for controlling opening degree of valve of nuclear power station

Abstract

The invention is suitable for the technical field of nuclear power station control, and provides a nuclear power station valve opening degree control method which comprises the steps that when a control system detects that a flow instrument breaks down and first output power is larger than first preset power, the valve opening degree of a first control valve is controlled to be the maximum opening degree, the first output power is real-time output power, obtained through the control system, of the steam generator; and the valve opening degree of the second control valve is adjusted according to second output power, and the second output power is the real-time output power, obtained through the control system, of the steam generator and is larger than the first output power. The method can timely and accurately control the opening degree of the water flow control valve and reduce the loss of the nuclear power station.

Description

Technical Field

[0001] This application belongs to the field of nuclear power plant control technology, and in particular relates to a method and control system for controlling the valve opening degree of a nuclear power plant. Background Technology

[0002] In the safe and efficient operation of nuclear power plants, steam generator flow meters play a crucial role. As one of the core components of the nuclear power plant's thermal system, the steam generator is responsible for converting the heat generated by the nuclear reactor into steam, which then drives the turbine generator to produce electricity. In this process, flow meters not only monitor the water flow velocity inside the steam generator to ensure stable system operation, but also directly participate in the precise control of the main control valve opening to maintain optimal operating conditions. Therefore, the accuracy and reliability of the flow meters directly affect the safety and economy of the entire nuclear power plant. However, in actual operation, flow meters may encounter various malfunctions, such as sensor failure, data transmission errors, or control system failures in the steam generator of the primary loop of a nuclear power plant. Once these problems occur, operators will be unable to obtain accurate flow data in a timely manner, making effective intervention and adjustments difficult. Especially in emergency situations, the opening control of the main control valve becomes paramount; any delay or misjudgment can lead to serious consequences, including equipment damage, system shutdown, or even a nuclear safety accident. Summary of the Invention

[0003] This application provides a method and control system for controlling the valve opening degree in a nuclear power plant, which can control the opening degree of the water flow control valve in a timely and accurate manner, thereby reducing losses in the nuclear power plant.

[0004] In a first aspect, embodiments of this application provide a method for controlling the valve opening degree of a nuclear power plant, applied to a control system of a steam generator in a primary loop. The control system includes a flow meter connected to the steam generator, a first control valve, and a second control valve. The control system regulates the water flow rate and / or steam flow rate entering the steam generator by controlling the valve opening degree of the first control valve and / or the second control valve. The flow meter is used to monitor the water supply flow rate and / or steam flow rate of the steam generator. The control method includes: When the control system detects that the flow meter has malfunctioned and the first output power is greater than the first preset power, it controls the valve opening of the first control valve to the maximum opening, wherein the first output power is the real-time output power of the steam generator obtained by the control system; The valve opening of the second control valve is adjusted according to the second output power, where the second output power is the real-time output power of the steam generator obtained through the control system and is greater than the first output power.

[0005] In this embodiment, when a flow meter malfunction is detected and the output power is greater than the system's set power, the system controls the valve opening based on the current output power. This avoids the system controlling the water level control valve opening based on the flow value of the malfunctioning flow meter, which could lead to abnormal valve opening of the main water level control valve. The above method can control the main control valve opening in a timely and accurate manner, reducing losses in nuclear power plants.

[0006] In one possible implementation of the first aspect, before the step of controlling the valve opening of the first control valve to the maximum opening when the control system detects a malfunction in the flow meter and the first output power is greater than a first preset power, the control method further includes: Obtain the first water supply flow rate value, which is the water supply flow rate value currently displayed by the flow meter; Based on the first water supply flow rate value, determine the first valve opening of the second control valve; Based on the first valve opening and the second valve opening, it is determined whether the flow meter has malfunctioned. The second valve opening is the valve opening of the second control valve determined when the output power of the steam generator is at its maximum output power.

[0007] In one possible implementation of the first aspect, the flow meter is a plurality of instruments, including a plurality of first flow meters and a plurality of second flow meters. The plurality of first flow meters are used to monitor the water supply flow rate of the steam generator, and the plurality of second flow meters are used to monitor the steam flow rate of the steam generator. The step of determining whether the flow meter has malfunctioned based on the first valve opening and the second valve opening includes: When the water supply flow values ​​corresponding to the multiple first flow meters are different, and the steam flow values ​​corresponding to the multiple second flow meters are the same, the second water supply flow value, the third water supply flow value, and the first steam flow value are obtained; wherein, the second water supply flow value is the minimum value corresponding to the water supply flow value among the multiple first flow meters, the third water supply flow value is the maximum value corresponding to the water supply flow value among the multiple first flow meters, and the first steam flow value is any steam flow value among the multiple second flow meters; If the first difference is greater than the first preset threshold, the second difference is greater than the second preset threshold, and the third difference is greater than the third preset threshold, then it is determined that the first flow meter corresponding to the second water supply flow value has malfunctioned. The first difference is the difference between the first valve opening and the second valve opening, the second difference is the difference between the second water supply flow value and the first steam flow value, and the third difference is the difference between the third water supply flow value and the second water flow value.

[0008] In one possible implementation of the first aspect, the method further includes: When the water supply flow values ​​corresponding to multiple first flow meters are the same, and the steam flow values ​​corresponding to multiple second flow meters are the same, if the first difference is less than the fourth preset threshold, then the fourth water supply flow value corresponding to the maximum output power of the control system of the steam generator in the primary loop of the nuclear power plant is calculated. If the fourth water supply flow value is the same as the water supply flow value corresponding to any of the first flow meters, then calculate the fourth difference between the fourth water supply flow value and the second steam flow value corresponding to any of the second flow meters. If the fourth difference is less than the fifth preset threshold, it is determined that all of the second flow meters have malfunctioned; wherein the fourth preset threshold is the opposite of the first preset threshold; and the fifth preset threshold is the opposite of the second preset threshold.

[0009] In one possible implementation of the first aspect, the step of adjusting the valve opening of the second control valve according to the second output power includes: The third valve opening of the second control valve is calculated based on the second output power and the preset valve opening function; wherein, the preset valve opening function is a function generated based on multiple sets of historical valve opening data; A valve adjustment command containing the third valve opening is generated and sent to the second control valve, the valve adjustment command being used to instruct the second control valve to adjust its valve opening to the third valve opening.

[0010] In one possible implementation of the first aspect, before the step of controlling the valve opening of the first control valve to the maximum opening when the control system detects a malfunction in the flow meter and the first output power is greater than a first preset power, the control method further includes: When the control system does not detect a malfunction in the flow meter, if the real-time output power of the steam generator is less than the second preset power, it controls the first control valve to adjust to the first valve opening and closes the second control valve. If the real-time output power of the steam generator is greater than the second preset power and less than the first preset power, the second control valve is controlled to adjust to the first valve opening degree; wherein, the second preset power is less than the first preset power.

[0011] In one possible implementation of the first aspect, the control system of the steam generator in the primary loop of the nuclear power plant includes a control component for indicating whether the flow meters of the control system of the steam generator in the primary loop of the nuclear power plant have malfunctioned; the method further includes: If a malfunction is detected in the flow meter, a prompt message is sent; wherein the prompt message is used to instruct the user to operate the control component; In response to a first operation by the user on the control component, the valve opening of the second control valve is controlled to be the opening degree corresponding to the first operation.

[0012] Secondly, embodiments of this application provide a control device for the valve opening degree of a nuclear power plant, comprising: The fault detection module is used to control the valve opening of the first control valve to the maximum opening when the control system detects that the flow meter has malfunctioned and the first output power is greater than the first preset power. The first output power is the real-time output power of the steam generator obtained by the control system. The fault control module is used to adjust the valve opening of the second control valve according to the second output power, wherein the second output power is the real-time output power of the steam generator obtained by the control system and is greater than the first output power.

[0013] Thirdly, embodiments of this application provide a terminal device, including a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein the processor executes the computer program to implement the control method as described in any one of the first aspects above.

[0014] Fourthly, embodiments of this application provide a computer-readable storage medium storing a computer program that, when executed by a processor, implements the control method as described in any one of the first aspects above.

[0015] Fifthly, embodiments of this application provide a computer program product that, when run on a terminal device, causes the terminal device to execute the control method described in any one of the first aspects.

[0016] It is understood that the beneficial effects of the second to fourth aspects mentioned above can be found in the relevant descriptions in the first aspect mentioned above, and will not be repeated here. Attached Figure Description

[0017] To more clearly illustrate the technical solutions in the embodiments of this application, the drawings used in the description of the embodiments or the prior art will be briefly introduced below. Obviously, the drawings described below are only some embodiments of this application. For those skilled in the art, other drawings can be obtained based on these drawings without creative effort.

[0018] Figure 1 This is a schematic diagram of a steam generator provided in an embodiment of this application; Figure 2 This is a flowchart illustrating the method for controlling the valve opening degree of a nuclear power plant according to an embodiment of this application; Figure 3 This is a schematic diagram of the process for detecting flow meter malfunctions provided in an embodiment of this application. Figure 1 ; Figure 4 This is a schematic diagram of the process for detecting flow meter malfunctions provided in an embodiment of this application. Figure 2 ; Figure 5 This is a schematic diagram of a single flow meter fault provided in an embodiment of this application; Figure 6 This is a schematic diagram of the process for detecting flow meter malfunctions provided in an embodiment of this application. Figure 3 ; Figure 7 This is a schematic diagram of a dual-meter flow meter fault provided in an embodiment of this application; Figure 8 This is a schematic diagram of the valve command control process provided in the embodiments of this application; Figure 9 This is a schematic diagram of the valve opening function provided in the embodiments of this application; Figure 10 This is a schematic diagram of the control component provided in an embodiment of this application; Figure 11 This is a structural block diagram of the control of valve opening in a nuclear power plant provided in an embodiment of this application; Figure 12 This is a schematic diagram of the structure of the terminal device provided in the embodiments of this application. Detailed Implementation

[0019] In the following description, specific details such as particular system architectures and techniques are set forth for illustrative purposes and not for limitation, in order to provide a thorough understanding of the embodiments of this application. However, those skilled in the art will understand that this application may also be implemented in other embodiments without these specific details. In other instances, detailed descriptions of well-known systems, apparatuses, circuits, and methods have been omitted so as not to obscure the description of this application with unnecessary detail.

[0020] It should be understood that, when used in this application specification and the appended claims, the term "comprising" indicates the presence of the described features, integrals, steps, operations, elements and / or components, but does not exclude the presence or addition of one or more other features, integrals, steps, operations, elements, components and / or a collection thereof.

[0021] It should also be understood that the term “and / or” as used in this application specification and the appended claims means any combination of one or more of the associated listed items and all possible combinations, and includes such combinations.

[0022] As used in this application specification and the appended claims, the term "if" may be interpreted, depending on the context, as "when," "once," "in response to determination," or "in response to detection." Similarly, the phrase "if determined" or "if detected [the described condition or event]" may be interpreted, depending on the context, as meaning "once determined," "in response to determination," "once detected [the described condition or event]," or "in response to detection [the described condition or event]."

[0023] Furthermore, in the description of this application and the appended claims, the terms "first," "second," "third," etc., are used only to distinguish descriptions and should not be construed as indicating or implying relative importance.

[0024] References to "one embodiment" or "some embodiments" in this specification mean that one or more embodiments of this application include a specific feature, structure, or characteristic described in connection with that embodiment. Therefore, the phrases "in one embodiment," "in some embodiments," "in other embodiments," "in still other embodiments," etc., appearing in different parts of this specification do not necessarily refer to the same embodiment, but rather mean "one or more, but not all, embodiments," unless otherwise specifically emphasized.

[0025] The steam generator is a key piece of equipment in a nuclear power plant. It is responsible for converting the heat energy generated by the nuclear reactor into steam to power the generator units. The steam generator flow meter plays a vital role in the safe and efficient operation of the nuclear power plant. It undertakes the core monitoring, control and safety assurance functions in the nuclear power plant system, and its role runs through the entire process of nuclear power plant operation.

[0026] See Figure 1 This is a schematic diagram of the steam generator system structure provided in the embodiments of this application, as shown below. Figure 1As shown, the nuclear power plant has three steam generators, SG1 / 2 / 3. Each steam generator corresponds to multiple flow meters, including water flow meters ARE043MD and ARE046MD, and steam flow meters VVP043MD and VVP046MD. Taking SG1 as an example, during power operation, the main control valve 031VL controls the main water supply flow to match the steam flow rates VVP001MD and VVP004MD to maintain a stable water level in the steam generator. When a flow meter malfunctions (either the water or steam flow meter), if the main control valve is controlled based on the flow meter readings, the valve may abnormally close or open, leading to abnormal changes in the steam generator water level. When the protection setpoint is reached, it can cause the reactor to shut down, thus requiring timely intervention.

[0027] However, when flow meters malfunction in a nuclear power plant's steam generator, manual intervention requires numerous steps and takes too long. Rapid manual control cannot precisely adjust the valve opening to control the water flow into the steam generator, posing a risk of intervention errors. A nuclear power plant previously experienced a reactor automatic shutdown due to delayed operator intervention, resulting in significant losses.

[0028] The short time frame and numerous operations leave operators with limited time to think and act, resulting in a low probability of successful intervention when flow meter malfunctions. Therefore, there is an urgent need for a method and device for automatic diagnosis and one-click sequential control intervention of flow meter malfunctions.

[0029] To address the aforementioned issues, this application provides a method and control system for controlling the valve opening of a nuclear power plant. In this application, when a flow meter malfunctions and the output power of the control system of the steam generator in the primary loop of the nuclear power plant exceeds the system's set power, the opening of the first control valve and / or the second control valve is adjusted based on the current output power of the control system of the steam generator in the primary loop of the nuclear power plant to regulate the water flow and / or steam flow entering the steam generator. This prevents the steam generator's control system from controlling the water level control valve's opening based on the flow rate value of the malfunctioning water or steam flow meter, which could lead to abnormal opening of the second control valve controlling the water level. This method can control the valve opening of the second control valve promptly and accurately, reducing losses at the nuclear power plant.

[0030] See Figure 2This is a flowchart illustrating a method for controlling the valve opening of a nuclear power plant according to an embodiment of this application. It is applied to the control system of a steam generator in the primary loop of a nuclear power plant. The control system includes a flow meter connected to the steam generator, a first control valve, and a second control valve. The control system regulates the water flow rate and / or steam flow rate entering the steam generator by controlling the valve opening of the first control valve and / or the second control valve. The flow meter is used to monitor the water supply flow rate and / or steam flow rate of the steam generator. As an example and not a limitation, the method may include the following steps: S101, when the control system detects that the flow meter has malfunctioned and the first output power is greater than the first preset power, it controls the valve opening of the first control valve to the maximum opening, wherein the first output power is the real-time output power of the steam generator obtained by the control system when the flow meter malfunctions.

[0031] In the embodiments of this application, such as Figure 2 In the control system of the steam generator in the primary loop of the nuclear power plant corresponding to the SG1 loop shown, the first control valve is the 242VL control valve corresponding to this loop, which can be called the secondary control valve. When a fault is detected in the SG1 control system, and the current real-time output power (first output power) of the SG1 control system exceeds the preset safety threshold (first preset power), the SG1 control system will automatically execute a series of emergency operations, adjusting the opening of the secondary control valve, i.e., the first control valve, which is responsible for controlling the water flow, to the maximum opening.

[0032] By maximizing the water flow rate of the first control valve, the cooling water volume (or process water volume) in the system is rapidly increased, thereby removing more heat or adjusting the state of the medium, thus reducing the safety risks that may be caused by excessive power. This is an emergency protection mechanism designed to ensure system safety.

[0033] S102, adjust the valve opening of the second control valve according to the second output power, wherein the second output power is the real-time output power of the steam generator obtained by the control system and is greater than the first output power.

[0034] In this embodiment, the second control valve is as follows: Figure 2The 031VL control valve in the SG1 circuit shown is also called the main control valve. As the second control valve of the main control valve, its opening degree is adjusted according to the current real-time output power of the system (i.e., the second output power). Since the first and second control valves are jointly responsible for controlling the water flow into the steam generator SG1, and the second output power is greater than the first output power, when the system is operating in the high output power range, the main control valve (second control valve) will dynamically adjust the valve opening according to the real-time second output power value. By precisely controlling the water inlet flow to match the steam generation demand under higher power, it ensures that the steam generator SG1 can operate stably and efficiently under high power conditions, and works with the auxiliary control valve (first control valve) to form a graded or coordinated control of the water inlet flow.

[0035] In the above method, when a flow meter malfunction is detected and the output power is greater than the system's set power, the system adjusts the opening of the first control valve and / or the second control valve based on the current output power. This avoids the system controlling the opening of the second control valve based on the flow value of the malfunctioning flow meter, which could lead to abnormal valve opening of the second control valve. The above method can control the opening of the second control valve in a timely and accurate manner, reducing losses at the nuclear power plant. In one embodiment, see Figure 3 This is a schematic diagram of the process for detecting flow meter malfunctions provided in an embodiment of this application. Figure 1 ,like Figure 3 As shown, before the step of controlling the valve opening of the first control valve to the maximum opening when the control system detects a malfunction in the flow meter and the first output power is greater than the first preset power, the control method further includes: S201, Obtain the first water supply flow rate value, where the first water supply flow rate value is the water supply flow rate value currently displayed by the flow meter.

[0036] In this embodiment, the control system of the SG1 generator needs to obtain the specific flow rate value displayed on the screen of the "flow meter" (a device specifically for monitoring the flow rate of the water supply pipeline) at this moment, which represents "water being supplied to the steam generator"—this real-time value is called the "first water supply flow rate value". The core is that the control system of SG1 establishes a connection with the flow meter and synchronizes the current real-time water supply flow rate data of the flow meter.

[0037] Specifically, for the flow meter, a smart flow meter with electronic signal output function can be selected (such as a meter that supports 4-20mA current signal and RS485 communication protocol), and it can be connected to the control system of the steam generator (such as PLC, dedicated fault control module) through a line / communication interface. The flow meter monitors the water flow velocity in the water supply pipeline in real time, calculates the current water supply flow rate, and converts it into an electronic signal that the control system can recognize. The SG1 control system continuously receives this real-time signal and automatically parses the signal into readable numbers (for example, converting the current signal from the meter into "8 m³ / h"). This parsed real-time number is the "first water supply flow rate value" obtained by the control system (no manual intervention is required throughout the process, and the control system actively / passively synchronizes the current data of the meter).

[0038] S202, determine the first valve opening of the second control valve based on the first water supply flow rate value.

[0039] In this embodiment, after the control system of SG1 obtains the first water supply flow value corresponding to the flow meter, it calculates the opening value that the second control valve should reach (i.e., the first valve opening) through a preset algorithm (such as the correspondence between flow value and opening degree, adjustment formula, etc.). This is used as the basis for adjusting the valve opening degree of the second control valve, and finally realizes the precise control of the water flow entering the steam generator to ensure that the flow meets the system operation requirements.

[0040] Specifically, the SG1 control system (such as PLC and dedicated fault control module) has pre-stored pre-set control rules (such as PID algorithm and fixed corresponding curve), which clearly defines "how much valve opening should correspond to different water supply flow rates" (for example, if the target water supply flow rate is 15 m³ / h, and the current first water supply flow rate is 12 m³ / h, the algorithm calculates that the valve needs to be opened to 60% to make up for the target flow rate). After the SG1 control system obtains the "first water supply flow rate value", it automatically substitutes it into the preset rules / algorithm to calculate and directly obtain the corresponding valve opening (such as 60%).

[0041] S203, determine whether the flow meter has malfunctioned based on the first valve opening and the second valve opening, wherein the second valve opening is the valve opening of the second control valve determined when the output power of the steam generator is at its maximum output power.

[0042] In the embodiments of this application, there are "first valve opening" (the opening of the second control valve determined in real time according to the current water supply flow) and "second valve opening" (the fixed opening of the second control valve when the output power of the steam generator is pulled to the maximum); by comparing these two openings, it is determined whether the "flow meter" monitoring the water supply flow is malfunctioning (such as inaccurate readings or abnormal signals).

[0043] When SG1 outputs maximum power, the required water flow rate is fixed. At this point, the second control valve must be opened to its maximum opening degree (e.g., 80%) to meet the water supply demand at maximum power, and the corresponding flow meter should display the maximum required flow rate. If, in reality, the second control valve is already open to its maximum opening degree (80%), but the calculated "first valve opening degree" based on the flow meter reading deviates significantly from 80% (e.g., only 30% is needed), then the flow meter reading is unreliable and a malfunction is highly probable.

[0044] In one embodiment, see Figure 4 This is a schematic diagram of the process for detecting flow meter malfunctions provided in an embodiment of this application. Figure 2 ,like Figure 4 As shown, there are multiple flow meters, including multiple first flow meters and multiple second flow meters. The multiple first flow meters are used to monitor the water supply flow rate of the steam generator, and the multiple second flow meters are used to monitor the steam flow rate of the steam generator. The step of determining whether the flow meter is malfunctioning based on the opening degree of the first valve and the second valve includes: S301, when the water supply flow values ​​corresponding to the multiple first flow meters are different, and the steam flow values ​​corresponding to the multiple second flow meters are the same, the second water supply flow value, the third water supply flow value, and the first steam flow value are obtained; wherein, the second water supply flow value is the minimum value corresponding to the water supply flow value among the multiple first flow meters, the third water supply flow value is the maximum value corresponding to the water supply flow value among the multiple first flow meters, and the first steam flow value is any steam flow value among the multiple second flow meters.

[0045] In this embodiment, there are two types of flow meters (first and second), and multiple of each type. The first type is specifically for measuring the "water supply flow" of the steam generator, and the second type is specifically for measuring the "steam flow". When determining whether these meters are faulty, we first consider a prerequisite: if the water supply flow readings of all the first flow meters are different (different from each other), but the steam flow readings of all the second flow meters are the same (consistent), then under this prerequisite, we extract three key values: the smallest water supply flow in the first flow meters (called the second water supply flow value), the largest water supply flow in the first flow meters (called the third water supply flow value), and the steam flow of any one of the second flow meters (called the first steam flow value), to prepare for subsequent fault diagnosis.

[0046] The reason for first looking at the premise that "the first flow meter readings are different while the second flow meter readings are the same" is that when the second flow meter readings are consistent, it indicates that the measurement on the steam side is stable and reliable (it is highly likely that the second flow meter is not faulty). At this time, if the first flow meter readings are inconsistent, it is highly likely that the first flow meter itself is faulty (rather than the actual fluctuations in the water / steam system). Therefore, it is necessary to extract the extreme values ​​of the first flow meter and the unified values ​​of the second flow meter to further verify the fault of the first flow meter.

[0047] S302, if the first difference is greater than the first preset threshold, the second difference is greater than the second preset threshold, and the third difference is greater than the third preset threshold, then it is determined that the first flow meter corresponding to the second water supply flow value has malfunctioned. The first difference is the difference between the first valve opening and the second valve opening, the second difference is the difference between the second water supply flow value and the first steam flow value, and the third difference is the difference between the third water supply flow value and the second water flow value.

[0048] In this embodiment, the first difference is the difference between the previously determined "first valve opening" and "second valve opening" (fixed opening under maximum power); the second difference is the difference between the "second water supply flow value" (minimum water supply flow of the first flow meter) and the "first steam flow value" (uniform steam flow of the second flow meter); the third difference is the difference between the "third water supply flow value" (maximum water supply flow of the first flow meter) and the "second water supply flow value" (minimum water supply flow of the first flow meter); if all three differences exceed their respective preset thresholds (the first, second, and third preset thresholds are pre-set judgment criteria), then it is determined that the first flow meter providing the "second water supply flow value" (that is, the one that measured the minimum water supply flow) has malfunctioned.

[0049] Its core logic is: The first difference exceeding the threshold indicates that the valve opening corresponding to the current flow rate (first valve opening) and the valve opening that should be under maximum power (second valve opening) are too far apart, which itself suggests that the water supply flow measurement may be inaccurate; The second difference exceeds the threshold: the deviation between the minimum water supply flow rate and the stable steam flow rate is too large. Because steam is generated by heating the water supply, under normal circumstances there is a reasonable correspondence between the two flow rates. If the deviation is too large, it means that the measurement of the minimum water supply flow rate is unreliable. The third difference exceeds the threshold: the difference between the maximum and minimum water supply flow of the first flow meter is too large, indicating that the reading dispersion among the first flow meters is extremely high, further confirming that there is an instrument measurement abnormality. When all three conditions are met, after excluding other factors such as system fluctuations, the fault is identified as the first flow meter that "measured the minimum water supply flow" (i.e. the meter corresponding to the second water supply flow value) malfunctioning (e.g., the reading is seriously too low, or the measurement is distorted).

[0050] Specifically, the SG1 control system pre-stores all basic data and preset thresholds—the opening degree of the first / second valve, the value of the second / third water supply flow rate, the value of the first steam flow rate, and the first, second, and third preset thresholds (set via program or entered through the operation panel); and the control system automatically calculates three differences: it calls up the data to calculate the first difference (|first valve opening degree - second valve opening degree|, taking the absolute value to avoid positive and negative influences); it calculates the second difference (|second water supply flow rate value - first steam flow rate value|); and it calculates the third difference (|third water supply flow rate value - second water supply flow rate value|).

[0051] Then, the system automatically performs three threshold comparisons: ① determining whether the first difference is greater than the first preset threshold; ② determining whether the second difference is greater than the second preset threshold; ③ determining whether the third difference is greater than the third preset threshold. If all three comparison results are "yes" (simultaneously satisfied), the system automatically determines that the first flow meter corresponding to the second water supply flow value is faulty and triggers subsequent actions (such as popping up a fault alarm, recording the faulty meter number, and switching to the backup measurement mode).

[0052] Exemplary, exemplary, see Figure 5 This is a schematic diagram of a single flow meter fault provided in an embodiment of this application, such as... Figure 5 As shown, when the flow rate values ​​corresponding to each first flow meter are different, and the flow rate values ​​corresponding to each second flow meter are the same, for example, the flow rate value of ARE043MD in the first flow meter is 1500t / h, the flow rate value of ARE046MD in the first flow meter is 1935t / h, and the flow rates of the second flow meters (steam flow) VVP001MD and VVP004MD are both 1935t / h.

[0053] At this point, the valve opening requirement (first opening) of the main control valve 031VL (second control valve) in the SG1 control system increases, exceeding the valve opening (second valve opening) set by the nuclear power (RPN010MA) by 10% (first preset threshold). This indicates an anomaly in the control system of the steam generator in the primary loop of the nuclear power plant, with the valve abnormally widened. Further comparison is needed between the maximum flow rate value (1935 t / h) in the second flow meter and the minimum flow rate value (1500 t / h) in the first flow meter, with a second difference (435 t / h). This second difference is greater than 100 t / h. / h (second preset threshold), and finally compare the deviation between ARE043MD and ARE046MD of the first flow meter. The third difference a is 435t / h, which exceeds the third preset threshold of 80t / h (the second difference between the two second flow meters is calculated when the flow values ​​corresponding to each first flow meter are different and the flow values ​​corresponding to each second flow meter are the same). If all of the above are true, then it is determined whether the core power of the system is above 70%. If all of the above are true, it can be determined that the first flow meter (ARE043MD) has a drift fault.

[0054] It should be noted that when the flow rate values ​​corresponding to each first flow meter are the same, but the flow rate values ​​corresponding to each second flow meter are different, a third difference is calculated between the maximum and minimum steam flow rates of the second flow meters. The first, second, and third differences are then compared. If the first, second, and third differences satisfy the first, second, and third preset thresholds, respectively, then the second flow meter corresponding to the minimum steam flow rate is determined to be faulty. The second preset threshold is always greater than both the first and third preset thresholds.

[0055] In one implementation, see Figure 6 This is a schematic diagram of the process for detecting flow meter malfunctions provided in an embodiment of this application. Figure 3 ,like Figure 6 As shown, the method further includes: S401, when the water supply flow values ​​corresponding to the multiple first flow meters are the same, and the steam flow values ​​corresponding to the multiple second flow meters are the same, if the first difference is less than the fourth preset threshold, then calculate the fourth water supply flow value corresponding to the maximum output power of the control system of the steam generator in the primary loop of the nuclear power plant.

[0056] In this embodiment, when the readings of all first flow meters (measuring water flow) are consistent, and the readings of all second flow meters (measuring steam flow) are also consistent (indicating that the current water and steam measurement data are stable and reliable), if the "first difference" (the difference between the opening of the first valve and the opening of the second valve) is less than the pre-set "fourth preset threshold" (meaning that the deviation between the current valve opening and the standard opening at maximum power is not large), a specific value needs to be calculated. This value is "the water flow value that the steam generator control system in the primary loop of the nuclear power plant should correspond to at maximum output power", which we call the "fourth water flow value" (note: the "fourth water flow value" here is different from the previous definition of the maximum value of the first flow meter, and is a new definition specifically for "the standard water flow corresponding to maximum power").

[0057] S402, if the fourth water supply flow value is the same as the water supply flow value corresponding to any of the first flow meters, then calculate the fourth difference between the fourth water supply flow value and the second steam flow value corresponding to any of the second flow meters.

[0058] In this embodiment, it is first determined whether the "fourth water supply flow value" (the previously calculated standard water supply flow that should correspond to the maximum output power of the steam generator) is equal to (or considered the same within an allowable small error) the water supply flow value currently displayed by any first flow meter (measuring water supply flow). If they are equal, a "fourth difference" is calculated - this difference is the difference between the "fourth water supply flow value" and the steam flow value currently displayed by any second flow meter (measuring steam flow) (called the second steam flow value).

[0059] The "fourth water supply flow rate value" is the standard water supply flow rate under maximum power. When it is the same as the actual reading of the first flow meter, it means that the current water supply flow rate has just reached the standard value corresponding to the maximum power. At this time, it is necessary to further verify the matching of "water supply and steam". Steam is generated by heating the water supply. Under normal operating conditions, there is a fixed thermodynamic correspondence between the two flow rates (for example, the water supply flow rate determines the amount of steam generated). Calculating the difference between the two (the fourth difference) is to judge whether this correspondence is reasonable (for example, whether the difference is within the normal range, and then verify the accuracy of the instrument or whether the system operating conditions are normal).

[0060] S403, if the fourth difference is less than the fifth preset threshold, then it is determined that all of the second flow meters have malfunctioned; wherein, the fourth preset threshold is the opposite of the first preset threshold; and the fifth preset threshold is the opposite of the second preset threshold.

[0061] In this embodiment, the fourth preset threshold and the first preset threshold are "opposite numbers" (for example, if the first preset threshold is +5, the fourth is -5; the core is to determine the direction / deviation polarity correspondence, and in practical applications, absolute values ​​or reasonable ranges will be combined to avoid simple positive and negative influences). The fifth preset threshold and the second preset threshold are "opposite numbers". If the previously calculated "fourth difference" (the difference between the third water supply flow value and the second steam flow value) is less than this "fifth preset threshold", then it is determined that all the second flow meters (those meters that measure steam flow) have malfunctioned.

[0062] The judgment logic is as follows: It has been previously confirmed that "the third water supply flow rate (maximum power standard water supply flow rate) = the actual reading of the first flow meter", indicating that the water supply flow rate has reached the standard value corresponding to the maximum power. At this time, the "water supply - steam" should conform to a fixed thermodynamic correspondence (for example, the water supply flow rate determines the steam generation, and the difference between the two should be within a reasonable range). The fourth difference is the gap between the "standard water supply flow rate" and the "actual steam flow rate". If it is less than the "fifth preset threshold" (the opposite of the second preset threshold), it means that the actual steam flow rate deviates too much from the reasonable steam flow rate corresponding to the standard water supply flow rate (and the direction of deviation is opposite to the judgment direction of the second preset threshold). Since all the second flow meters read the same value (as previously assumed), but the steam flow rate they collectively displayed deviated too much from the "reasonable value corresponding to the standard water supply flow rate," it indicates that the problem was not with a single second flow meter, but rather that all the second flow meters were exhibiting the same measurement anomaly (such as uniform inaccuracy or signal offset). Therefore, it was determined that all the second flow meters were faulty.

[0063] For example, see Figure 7 This is a schematic diagram of a dual-meter flow meter fault provided in another embodiment of this application, such as... Figure 7 The flow rates of the first flow meters ARE043MD and ARE046MD are both 1935 t / h, while the flow rates of the second flow meters VVP001MD and VVP004MD are both 1500 t / h. At this time, the required opening degree (first valve opening) of the main control valve ARE031VL (second control valve) in the control system of the steam generator in the primary loop of the nuclear power plant becomes smaller, and is less than -10% (fourth preset threshold) of the valve opening degree (second valve opening) set for nuclear power (real-time output power, current output power is 70%), indicating that there is an abnormality in the control system of the steam generator in the primary loop of the nuclear power plant, and the valve is abnormally open.

[0064] In the above example, the abnormally small opening of the valve may be due to the first flow meter ARE043MD and the first flow meter ARE046MD malfunctioning upwards or the second flow meter VVP001MD and the second flow meter VVP004MD malfunctioning downwards. In this case, it is necessary to obtain the flow values ​​of the first flow meter and the second flow meter at 100% FP nuclear power setting for comparison.

[0065] When the flow rates of both the first and second flow meters are set to 1930 t / h at 100% FP nuclear power, the difference between the maximum value of the second flow meter (1500 t / h) and the flow rate set to 100% FP nuclear power (1930 t / h) (-430 t / h) (the fourth difference) is less than -100 t / h (the fifth preset threshold). Therefore, it can be determined that the second flow meter VVP001 / 004MD has malfunctioned and is drifting downwards. This malfunction causes the main control valve (i.e., the second control valve) to close slightly, resulting in a decrease in feedwater flow and a drop in the steam generator level below -0.1 m, ultimately leading to reactor shutdown.

[0066] The above method improves the reliability and safety of the control system for the steam generator in the primary loop of a nuclear power plant by employing multi-parameter detection, real-time data monitoring, and detailed fault location. It helps reduce operational errors, optimize maintenance plans, and enhance the overall performance and stability of the system.

[0067] In one embodiment, in one implementation, see Figure 8 This is a schematic diagram of the valve command control flow provided in the embodiments of this application, such as... Figure 8 As shown, step S102 includes: S501, the third valve opening of the second control valve is calculated based on the second output power and the preset valve opening function; wherein, the preset valve opening function is a function generated based on multiple sets of historical valve opening data.

[0068] In this embodiment, the valve opening function is typically a mathematical model or algorithm that generates an output based on input historical data. This function can be linear, nonlinear, statistical, or a machine learning model; for example, a simple linear model is used as the first function. , where x is the input historical data, and a and b are the parameters of the model.

[0069] See Figure 9 This is a schematic diagram of the valve opening function provided in the embodiments of this application, such as... Figure 9As shown, a linear function obtained by fitting multiple historical data can be used to obtain the opening degree of the third valve that needs to be adjusted by inputting the real-time output power of the control system of the steam generator in the primary loop of the nuclear power plant into the fitted linear function.

[0070] After obtaining the third opening degree, the valve of the first control valve is opened to the maximum opening degree, i.e., 100%, and the valve of the second control valve is opened to the third opening degree.

[0071] In the above method, historical data is used to generate a fitting function. The valve opening of the main control valve (i.e. the second control valve) is obtained by using the fitting function and the real-time output power of the control system of the steam generator in the primary loop of the nuclear power plant. This can improve system performance, reduce energy consumption, enhance system stability and safety, and simplify the maintenance process.

[0072] S502, a valve adjustment command including the third valve opening is generated and sent to the second control valve, the valve adjustment command being used to instruct the second control valve to adjust its valve opening to the third valve opening.

[0073] In this embodiment, based on the third valve opening generated above, a special "valve adjustment command" is generated (this command will explicitly contain the information "to adjust to the third valve opening"), and then this command is sent to the "second control valve". The ultimate goal is to make the second control valve adjust its current valve opening to the state of the third valve opening according to the command requirements (for example, from the current 50% to 70%).

[0074] In one embodiment, before the step of controlling the valve opening of the first control valve to the maximum opening when the control system detects a malfunction in the flow meter and the first output power is greater than a first preset power, the control method further includes: When the control system does not detect a malfunction in the flow meter, if the real-time output power of the steam generator is less than the second preset power, the first control valve is adjusted to the first valve opening, and the second control valve is closed; if the real-time output power of the steam generator is greater than the second preset power and less than the first preset power, the second control valve is adjusted to the first valve opening; wherein, the second preset power is less than the first preset power.

[0075] In this embodiment, when the control system of the steam generator confirms that all flow meters are functioning correctly, it performs different operations on the two control valves according to different ranges of real-time output power: ① If the real-time output power is lower than the "second preset power" (a lower power threshold), it controls the "first control valve" to adjust to the "first valve opening" and completely closes the "second control valve"; ② If the real-time output power is between the "second preset power" and the "first preset power" (a higher power threshold, and greater than the second preset power), it only controls the "second control valve" to adjust to the "first valve opening" (the state of the first control valve is not involved and is maintained or defaulted according to the previous logic).

[0076] In one embodiment, the control system of the steam generator in the primary loop of the nuclear power plant includes a control component for indicating whether the flow meters of the control system of the steam generator in the primary loop of the nuclear power plant have malfunctioned; the method further includes: If a malfunction is detected in the flow meter, a prompt message is sent; wherein the prompt message is used to instruct the user to operate the control component; in response to the user's first operation on the control component, the valve opening of the second control valve is controlled to be the opening degree corresponding to the first operation.

[0077] See the example in this application. Figure 10 This is a schematic diagram of the control component provided in an embodiment of this application, as shown below. Figure 10 As shown, the control system of the steam generator in the primary loop of the nuclear power plant includes a control component 401KC. This control component is an independent display device with button operation. If a malfunction of the flow meter (water flow meter or steam flow meter) is detected according to the above steps, a red frame and a "drift meter" indicator will appear on the outside of the control component to remind the operator to operate the control. After the operator presses the button on the control component (first operation), the control system of the steam generator in the primary loop of the nuclear power plant will immediately control the opening of the first control valve to its maximum (100%) and control the second control valve to its third opening. After the operator operates the control component, and after five seconds (the above sequential control is generally completed within five seconds), the opening of the second ARE031VL can be controlled according to the change in liquid level.

[0078] The above method incorporates fault detection and user interaction functions (control components), enabling the control system of the steam generator in the primary loop of a nuclear power plant to communicate more intelligently with users and provide solutions when a fault occurs. This not only improves the system's safety, reliability, and user-friendliness but also enhances its overall performance and maintenance efficiency. Through this design, the system can operate more flexibly and stably in the face of uncertainty.

[0079] This system is essentially an "add-on" to the existing control system of the steam generator in the primary loop of a nuclear power plant, which greatly facilitates operator control and intervention, and has significant potential for widespread adoption.

[0080] Corresponding to the control method for the valve opening of a nuclear power plant described in the above embodiments, Figure 11 This is a structural block diagram of the control of the valve opening degree of a nuclear power plant provided in the embodiments of this application. For ease of explanation, only the parts related to the embodiments of this application are shown.

[0081] Reference Figure 11 The valve opening control device of this nuclear power plant includes: The fault detection module 110 is used to control the valve opening of the first control valve to the maximum opening when the control system detects that the flow meter has malfunctioned and the first output power is greater than the first preset power, wherein the first output power is the real-time output power of the steam generator obtained by the control system. The control device 11 for the valve opening of the nuclear power plant also includes a fault indication module 111, used for: If a malfunction is detected in the flow meter, a prompt message is sent; wherein the prompt message is used to instruct the user to operate the control component; In response to a first operation by the user on the control component, the valve opening of the second control valve is controlled to be the opening degree corresponding to the first operation.

[0082] The fault control module 112 is used to adjust the valve opening of the second control valve according to the second output power, wherein the second output power is the real-time output power of the steam generator obtained by the control system and is greater than the first output power.

[0083] Optionally, the fault detection module 110 is also used for: Obtain the first water supply flow rate value, which is the water supply flow rate value currently displayed by the flow meter; Based on the first water supply flow rate value, determine the first valve opening of the second control valve; Based on the first valve opening and the second valve opening, it is determined whether the flow meter has malfunctioned. The second valve opening is the valve opening of the second control valve determined when the output power of the steam generator is at its maximum output power.

[0084] Optionally, the fault detection module 110 is also used for: When the water supply flow values ​​corresponding to the multiple first flow meters are different, and the steam flow values ​​corresponding to the multiple second flow meters are the same, the second water supply flow value, the third water supply flow value, and the first steam flow value are obtained; wherein, the second water supply flow value is the minimum value corresponding to the water supply flow value among the multiple first flow meters, the third water supply flow value is the maximum value corresponding to the water supply flow value among the multiple first flow meters, and the first steam flow value is any steam flow value among the multiple second flow meters; If the first difference is greater than the first preset threshold, the second difference is greater than the second preset threshold, and the third difference is greater than the third preset threshold, then it is determined that the first flow meter corresponding to the second water supply flow value has malfunctioned. The first difference is the difference between the first valve opening and the second valve opening, the second difference is the difference between the second water supply flow value and the first steam flow value, and the third difference is the difference between the third water supply flow value and the second water flow value.

[0085] Optionally, the fault detection module 110 is also used for: When the water supply flow values ​​corresponding to multiple first flow meters are the same, and the steam flow values ​​corresponding to multiple second flow meters are the same, if the first difference is less than the fourth preset threshold, then the third water supply flow value corresponding to the maximum output power of the control system of the steam generator in the primary loop of the nuclear power plant is calculated. If the third water supply flow value is the same as the water supply flow value corresponding to any of the first flow meters, then calculate the fourth difference between the third water supply flow value and the second steam flow value corresponding to any of the second flow meters. If the fourth difference is less than the fifth preset threshold, it is determined that all of the second flow meters have malfunctioned; wherein the fourth preset threshold is the opposite of the first preset threshold; and the fifth preset threshold is the opposite of the second preset threshold.

[0086] Optionally, the fault control module 112 is also used for: The third valve opening of the second control valve is calculated based on the second output power and the preset valve opening function; wherein, the preset valve opening function is a function generated based on multiple sets of historical valve opening data; A valve adjustment command containing the third valve opening is generated and sent to the second control valve, the valve adjustment command being used to instruct the second control valve to adjust its valve opening to the third valve opening.

[0087] It should be noted that the information interaction and execution process between the above-mentioned devices / units are based on the same concept as the method embodiments of this application. For details on their specific functions and technical effects, please refer to the method embodiments section, and they will not be repeated here.

[0088] in addition, Figure 11 The valve control device for the nuclear power plant valve shown can be a software unit, a hardware unit, or a combination of software and hardware built into the existing terminal equipment. It can also be integrated into the terminal equipment as an independent component, or it can exist as an independent terminal equipment.

[0089] It should be understood that the sequence number of each step in the above embodiments does not imply the order of execution. The execution order of each process should be determined by its function and internal logic, and should not constitute any limitation on the implementation process of the embodiments of this application.

[0090] Those skilled in the art will clearly understand that, for the sake of convenience and brevity, the above-described division of functional units and modules is merely an example. In practical applications, the above functions can be assigned to different functional units and modules as needed, that is, the internal structure of the device can be divided into different functional units or modules to complete all or part of the functions described above. The functional units and modules in the embodiments can be integrated into one processing unit, or each unit can exist physically separately, or two or more units can be integrated into one unit. The integrated unit can be implemented in hardware or as a software functional unit. Furthermore, the specific names of the functional units and modules are only for easy differentiation and are not intended to limit the scope of protection of this application. The specific working process of the units and modules in the above system can be referred to the corresponding process in the foregoing method embodiments, and will not be repeated here.

[0091] Figure 12 This is a schematic diagram of the structure of the terminal device provided in the embodiments of this application. For example... Figure 12 As shown, the terminal device 12 of this embodiment includes: at least one processor 120 ( Figure 12 (Only one is shown in the diagram) a processor, a memory 121, and a computer program 122 stored in the memory 121 and executable on the at least one processor 120, wherein the processor 120 executes the computer program 122 to implement the steps in any of the above control method embodiments.

[0092] The terminal device may be a desktop computer, laptop, handheld computer, or cloud server, etc. This terminal device may include, but is not limited to, a processor and memory. Those skilled in the art will understand that... Figure 12This is merely an example of terminal device 12 and does not constitute a limitation on terminal device 12. It may include more or fewer components than shown, or combine certain components, or different components, such as input / output devices, network access devices, etc.

[0093] The processor 120 may be a Central Processing Unit (CPU), or it may be other general-purpose processors, digital signal processors (DSPs), application-specific integrated circuits (ASICs), field-programmable gate arrays (FPGAs), or other programmable logic devices, discrete gate or transistor logic devices, discrete hardware components, etc. A general-purpose processor may be a microprocessor or any conventional processor.

[0094] In some embodiments, the memory 121 may be an internal storage unit of the terminal device 12, such as a hard disk or memory of the terminal device 12. In other embodiments, the memory 121 may be an external storage device of the terminal device 12, such as a plug-in hard disk, smart media card (SMC), secure digital (SD) card, flash card, etc., equipped on the terminal device 12. Furthermore, the memory 121 may include both internal and external storage units of the terminal device 12. The memory 121 is used to store the operating system, applications, boot loader, data, and other programs, such as the program code of the computer program. The memory 121 can also be used to temporarily store data that has been output or will be output.

[0095] This application also provides a computer-readable storage medium storing a computer program that, when executed by a processor, can implement the steps in the above-described method embodiments.

[0096] This application provides a computer program product that, when run on a terminal device, enables the terminal device to implement the steps described in the various method embodiments above.

[0097] If the integrated unit is implemented as a software functional unit and sold or used as an independent product, it can be stored in a computer-readable storage medium. Based on this understanding, all or part of the processes in the methods of the above embodiments of this application can be implemented by a computer program instructing related hardware. The computer program can be stored in a computer-readable storage medium, and when executed by a processor, it can implement the steps of the various method embodiments described above. The computer program includes computer program code, which can be in the form of source code, object code, executable files, or certain intermediate forms. The computer-readable medium can include at least: any entity or device capable of carrying computer program code to a device / terminal equipment, a recording medium, a computer memory, a read-only memory (ROM), a random access memory (RAM), an electrical carrier signal, a telecommunication signal, and a software distribution medium. Examples include USB flash drives, portable hard drives, magnetic disks, or optical disks. In some jurisdictions, according to legislation and patent practice, computer-readable media cannot be electrical carrier signals or telecommunication signals.

[0098] In the above embodiments, the descriptions of each embodiment have different focuses. For parts that are not described in detail or recorded in a certain embodiment, please refer to the relevant descriptions of other embodiments.

[0099] Those skilled in the art will recognize that the units and algorithm steps of the various examples described in conjunction with the embodiments disclosed herein can be implemented in electronic hardware, or a combination of computer software and electronic hardware. Whether these functions are implemented in hardware or software depends on the specific application and design constraints of the technical solution. Those skilled in the art can use different methods to implement the described functions for each specific application, but such implementation should not be considered beyond the scope of this application.

[0100] In the embodiments provided in this application, it should be understood that the disclosed devices / terminal equipment and methods can be implemented in other ways. For example, the device / terminal equipment embodiments described above are merely illustrative. For instance, the division of modules or units is only a logical functional division, and in actual implementation, there may be other division methods. For example, multiple units or components may be combined or integrated into another system, or some features may be ignored or not executed. Furthermore, the coupling or direct coupling or communication connection shown or discussed may be through some interfaces; the indirect coupling or communication connection between devices or units may be electrical, mechanical, or other forms.

[0101] The units described as separate components may or may not be physically separate. The components shown as units may or may not be physical units; that is, they may be located in one place or distributed across multiple network units. Some or all of the units can be selected to achieve the purpose of this embodiment according to actual needs.

[0102] The above-described embodiments are only used to illustrate the technical solutions of this application, and are not intended to limit them. Although this application has been described in detail with reference to the foregoing embodiments, those skilled in the art should understand that modifications can still be made to the technical solutions described in the foregoing embodiments, or equivalent substitutions can be made to some of the technical features. Such modifications or substitutions do not cause the essence of the corresponding technical solutions to deviate from the spirit and scope of the technical solutions of the embodiments of this application, and should all be included within the protection scope of this application.

Claims

1. A method for controlling the opening degree of a valve in a nuclear power plant, characterized in that, A control system applied to a steam generator in a primary loop, the control system including a flow meter connected to the steam generator, a first control valve, and a second control valve, the control system regulating the water flow rate and / or steam flow rate entering the steam generator by controlling the valve opening of the first control valve and / or the second control valve, the flow meter being used to monitor the water supply flow rate and / or steam flow rate of the steam generator, the control method including: When the control system detects that the flow meter has malfunctioned and the first output power is greater than the first preset power, it controls the valve opening of the first control valve to the maximum opening, wherein the first output power is the real-time output power of the steam generator obtained by the control system; The valve opening of the second control valve is adjusted according to the second output power, where the second output power is the real-time output power of the steam generator obtained through the control system and is greater than the first output power.

2. The method for controlling the valve opening degree of a nuclear power plant as described in claim 1, characterized in that, Before the step of controlling the opening degree of the first control valve to the maximum opening degree when the control system detects a malfunction in the flow meter and the first output power is greater than the first preset power, the control method further includes: Obtain the first water supply flow rate value, which is the water supply flow rate value currently displayed by the flow meter; Based on the first water supply flow rate value, determine the first valve opening of the second control valve; Based on the first valve opening and the second valve opening, it is determined whether the flow meter has malfunctioned. The second valve opening is the valve opening of the second control valve determined when the output power of the steam generator is at its maximum output power.

3. The method for controlling the valve opening degree of a nuclear power plant as described in claim 2, characterized in that, The flow meters are multiple, including multiple first flow meters and multiple second flow meters. The multiple first flow meters are used to monitor the water supply flow rate of the steam generator, and the multiple second flow meters are used to monitor the steam flow rate of the steam generator. The step of determining whether the flow meters are malfunctioning based on the opening degree of the first valve and the second valve includes: When the water supply flow values ​​corresponding to the multiple first flow meters are different, and the steam flow values ​​corresponding to the multiple second flow meters are the same, the second water supply flow value, the third water supply flow value, and the first steam flow value are obtained; wherein, the second water supply flow value is the minimum value corresponding to the water supply flow value among the multiple first flow meters, the third water supply flow value is the maximum value corresponding to the water supply flow value among the multiple first flow meters, and the first steam flow value is any steam flow value among the multiple second flow meters; If the first difference is greater than the first preset threshold, the second difference is greater than the second preset threshold, and the third difference is greater than the third preset threshold, then it is determined that the first flow meter corresponding to the second water supply flow value has malfunctioned. The first difference is the difference between the first valve opening and the second valve opening, the second difference is the difference between the second water supply flow value and the first steam flow value, and the third difference is the difference between the third water supply flow value and the second water flow value.

4. The method for controlling the valve opening degree of a nuclear power plant as described in claim 3, characterized in that, The method further includes: When the water supply flow values ​​corresponding to multiple first flow meters are the same, and the steam flow values ​​corresponding to multiple second flow meters are the same, if the first difference is less than the fourth preset threshold, then the fourth water supply flow value corresponding to the maximum output power of the control system of the steam generator in the primary loop of the nuclear power plant is calculated. If the fourth water supply flow value is the same as the water supply flow value corresponding to any of the first flow meters, then calculate the fourth difference between the fourth water supply flow value and the second steam flow value corresponding to any of the second flow meters. If the fourth difference is less than the fifth preset threshold, it is determined that all of the second flow meters have malfunctioned; wherein the fourth preset threshold is the opposite of the first preset threshold; and the fifth preset threshold is the opposite of the second preset threshold.

5. The method for controlling the valve opening degree of a nuclear power plant as described in claim 1, characterized in that, The step of adjusting the valve opening of the second control valve according to the second output power includes: The third valve opening of the second control valve is calculated based on the second output power and the preset valve opening function; wherein, the preset valve opening function is a function generated based on multiple sets of historical valve opening data; A valve adjustment command containing the third valve opening is generated and sent to the second control valve, the valve adjustment command being used to instruct the second control valve to adjust its valve opening to the third valve opening.

6. The method for controlling the valve opening degree of a nuclear power plant as described in claim 2, characterized in that, Before the step of controlling the opening degree of the first control valve to the maximum opening degree when the control system detects a malfunction in the flow meter and the first output power is greater than the first preset power, the control method further includes: When the control system does not detect a malfunction in the flow meter, if the real-time output power of the steam generator is less than the second preset power, it controls the first control valve to adjust to the first valve opening and closes the second control valve. If the real-time output power of the steam generator is greater than the second preset power and less than the first preset power, the second control valve is controlled to adjust to the first valve opening degree; wherein, the second preset power is less than the first preset power.

7. The method for controlling the valve opening degree of a nuclear power plant as described in claim 1, characterized in that, The control system for the steam generator in the primary loop of the nuclear power plant includes a control component, which is used to indicate whether the flow meters of the control system for the steam generator in the primary loop of the nuclear power plant are malfunctioning; the method further includes: If a malfunction is detected in the flow meter, a prompt message is sent; wherein the prompt message is used to instruct the user to operate the control component; In response to a first operation by the user on the control component, the valve opening of the second control valve is controlled to be the opening degree corresponding to the first operation.

8. A control device for the valve opening degree of a nuclear power plant, characterized in that, include: The fault detection module is used to control the valve opening of the first control valve to the maximum opening when the control system detects that the flow meter has failed and the first output power is greater than the first preset power. The first output power is the real-time output power of the steam generator obtained by the control system. The fault control module is used to adjust the valve opening of the second control valve according to the second output power, wherein the second output power is the real-time output power of the steam generator obtained through the control system and is greater than the first output power.

9. A terminal device, comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, characterized in that, When the processor executes the computer program, it implements the method as described in any one of claims 1 to 7.

10. A computer-readable storage medium storing a computer program, characterized in that, When the computer program is executed by a processor, it implements the method as described in any one of claims 1 to 7.

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