Fault early-warning method, system and device for nuclear reactor
By acquiring monitoring data of nuclear reactors in operating and simulated environments, calculating data deviations, and issuing early warnings, the problem of untimely early warnings caused by the lag in monitoring data has been solved, enabling real-time fault analysis and timely early warning of nuclear reactors.
Patent Information
- Application Number
- PCT/CN2025/092550
- Authority / Receiving Office
- WO · WO
- Patent Type
- Applications
- Current Assignee / Owner
- Priority Date
- 2024-05-31
- Filing Date
- 2025-04-30
- Publication Date
- 2025-12-04
AI Technical Summary
Existing nuclear reactor monitoring and early warning systems suffer from delayed warnings due to the lag in monitoring data, making it impossible to detect potential faults in a timely manner.
By acquiring monitoring data of the nuclear reactor in both operating and simulated environments, calculating data deviations, using third-party monitoring data to determine fault information and issue early warnings, and combining fault location and control parameter corrections, real-time analysis and early warning can be achieved.
It enables real-time fault warnings for nuclear reactors, improving the timeliness and accuracy of operators in detecting potential problems and reducing the probability of accidents.
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Figure CN2025092550_04122025_PF_FP_ABST
Abstract
Description
Methods, systems and equipment for early warning of nuclear reactor failures Technical Field
[0001] This application relates to the technical field of fault early warning for nuclear reactors, and in particular to a fault early warning method, system and equipment for nuclear reactors. Background Technology
[0002] The safe and stable operation of nuclear power plants is crucial to a nation's energy security and social development. Establishing a scientific, accurate, and reliable nuclear power monitoring and early warning system allows for real-time monitoring of key parameters, identification of potential faults and anomalies, and early warning for corresponding measures. A good monitoring and early warning system can also reduce the probability of accidents, lower the severity of accidents, mitigate the consequences of accidents, and improve emergency response capabilities. Therefore, the construction of nuclear power monitoring and early warning systems is an important component of the construction and operation of nuclear power plants in all countries.
[0003] In related technologies, nuclear power plant monitoring and early warning systems typically compare currently collected monitoring data with preset safety thresholds to determine if there are any anomalies in the nuclear reactor, thereby achieving early warning. However, because the collected monitoring data usually has a lag, early warnings for nuclear reactors are often untimely. Summary of the Invention
[0004] This application aims to propose a method, system, and device for early warning of nuclear reactor failures, which can analyze and monitor data in real time, provide early warning of abnormal situations, and help operators to promptly identify potential problems.
[0005] In a first aspect, embodiments of this application provide a method for early warning of nuclear reactor failures, comprising the following steps:
[0006] Acquire first monitoring data and second monitoring data at a first moment, wherein the first monitoring data is the data monitored by the monitoring components of the nuclear reactor in its operating environment, and the second monitoring data is the monitoring data of the nuclear reactor in a simulated environment;
[0007] If the deviation between the first monitoring data and the second monitoring data exceeds a preset threshold range, and it is determined that the monitoring component is normal, the third monitoring data of the nuclear reactor in the simulation environment at the second time point is obtained, where the second time point is the time after the first time point;
[0008] Based on the third monitoring data, fault information of the nuclear reactor at the second time point is determined, and the fault information is used to indicate whether there is a system fault in the nuclear reactor.
[0009] If the fault information indicates that there is a system fault in the nuclear reactor, an early warning prompt will be issued for the nuclear reactor.
[0010] In some implementations, after determining the fault information of the nuclear reactor at the second time point based on the third monitoring data, the method further includes:
[0011] When the fault information indicates that there is a system fault in the nuclear reactor, the fault location of the nuclear reactor is performed based on the third monitoring data to determine the faulty component of the nuclear reactor;
[0012] The control parameters of the faulty component of the nuclear reactor are corrected under the simulation environment to obtain corrected control parameters. Under the corrected control parameters, the nuclear reactor does not experience system failure under the simulation environment.
[0013] Output the corrected control parameters;
[0014] Based on the modified control parameters, the control parameters of the nuclear reactor in the operating environment are modified.
[0015] In some implementations, the step of locating the fault in the nuclear reactor based on the third monitoring data and identifying the faulty component of the nuclear reactor includes:
[0016] If the third monitoring data exceeds a preset safety threshold, the deviation between the third monitoring data and the preset safety threshold is calculated.
[0017] Based on the deviation between the third monitoring data and the preset safety threshold, the faulty component of the nuclear reactor is identified and an early warning notification for the nuclear reactor is issued.
[0018] In some implementations, when the deviation between the first monitoring data and the second monitoring data exceeds a preset threshold range, and it is determined that the monitoring component is functioning normally, acquiring third monitoring data of the nuclear reactor in a simulated environment at a second time point, where the second time point is a time after the first time point, includes:
[0019] If the deviation between the first monitoring data and the second monitoring data exceeds a preset threshold range, the validity of the first monitoring data is checked to determine whether the first monitoring data is valid.
[0020] If the first monitoring data is determined to be valid, the third monitoring data of the nuclear reactor in the simulated environment is obtained at a second time point, which is a time point after the first time point.
[0021] In some implementations, the validity check of the first monitoring data includes at least one of the following:
[0022] Based on the first monitoring data, determine whether the signal of the monitoring component contains distorted or pulse signals;
[0023] The target indicator of the first monitoring data is statistically analyzed to determine whether it is abnormal. The target indicator is used to measure at least one of the stability and repeatability of the data.
[0024] In some implementations, after determining whether the first monitoring data is valid data, the method further includes:
[0025] If the first monitoring data is determined to be invalid, it is determined whether the first monitoring data has a transient anomaly, wherein the transient anomaly is at least one of the following: the first monitoring data has a momentary fluctuation or jump signal.
[0026] If it is determined that there are no transient anomalies in the first monitoring data, the nuclear reactor is located based on the first monitoring data, the faulty component of the nuclear reactor is identified, and an early warning prompt is issued for the nuclear reactor.
[0027] In some implementations, the method further includes:
[0028] Based on the first monitoring data and the second monitoring data, the indicator parameter values of the target evaluation index are calculated, wherein the target evaluation index includes at least one of the MAD value and the MSE value;
[0029] Based on the second monitoring data and the preset threshold range, calculate the range of index parameters for the target evaluation index;
[0030] Based on the values and ranges of the aforementioned indicator parameters, the nuclear reactor system status anomaly is determined.
[0031] If it is determined that there is a system status anomaly in the nuclear reactor, a status anomaly prompt will be executed for the nuclear reactor.
[0032] Secondly, embodiments of this application provide a fault early warning system for a nuclear reactor, the fault early warning system for the nuclear reactor comprising:
[0033] The first data acquisition module is used to acquire first monitoring data and second monitoring data at a first moment. The first monitoring data is the data monitored by the monitoring components of the nuclear reactor in its operating environment, and the second monitoring data is the monitoring data of the nuclear reactor in a simulated environment.
[0034] The second data acquisition module is used to acquire third monitoring data of the nuclear reactor in the simulation environment at a second time when the deviation between the first monitoring data and the second monitoring data exceeds a preset threshold range and the monitoring component is determined to be normal; the second time is a time after the first time.
[0035] The fault determination module is used to determine the fault information of the nuclear reactor at the second time based on the third monitoring data, and the fault information is used to indicate whether there is a system fault in the nuclear reactor;
[0036] The early warning module is used to issue an early warning notification for the nuclear reactor when the fault information indicates that there is a system fault in the nuclear reactor.
[0037] Thirdly, embodiments of this application provide a fault early warning electronic device for a nuclear reactor, including at least one control processor and a memory for communicatively connecting to the at least one control processor; the memory stores instructions executable by the at least one control processor, which, when executed by the at least one control processor, enables the at least one control processor to perform the aforementioned fault early warning method for a nuclear reactor.
[0038] Fourthly, embodiments of this application provide a computer-readable storage medium storing computer-executable instructions for causing a computer to execute the aforementioned nuclear reactor fault early warning method.
[0039] In this embodiment, by acquiring first and second monitoring data at a first moment, where the first monitoring data is data monitored by monitoring components in the nuclear reactor's operating environment and the second monitoring data is monitoring data of the nuclear reactor in a simulated environment; if the deviation between the first and second monitoring data exceeds a preset threshold range and the monitoring components are determined to be normal, third monitoring data of the nuclear reactor in the simulated environment at a second moment, where the second moment is a time after the first moment; based on the third monitoring data, fault information of the nuclear reactor at the second moment is determined, and the fault information is used to indicate whether a system fault exists in the nuclear reactor; if the fault information indicates that a system fault exists in the nuclear reactor, an early warning prompt is executed for the nuclear reactor. Thus, based on the third monitoring data, fault information of the nuclear reactor at the second moment can be determined, thereby enabling real-time analysis of monitoring data, early warning of abnormal situations, and helping operators to promptly identify potential problems.
[0040] Additional aspects and advantages of this application will be set forth in part in the description which follows, and in part will be obvious from the description, or may be learned by practice of this application. Attached Figure Description
[0041] The above and / or additional aspects and advantages of this application will become apparent and readily understood from the description of the embodiments taken in conjunction with the following drawings, in which:
[0042] Figure 1 is a flowchart of an embodiment of the nuclear reactor fault early warning method provided in this application;
[0043] Figure 2 is another flowchart of an embodiment of the nuclear reactor fault early warning method provided in this application;
[0044] Figure 3 is another flowchart of an embodiment of the nuclear reactor fault early warning method provided in this application;
[0045] Figure 4 is another flowchart of an embodiment of the nuclear reactor fault early warning method provided in this application;
[0046] Figure 5 is another flowchart of an embodiment of the nuclear reactor fault early warning method provided in this application;
[0047] Figure 6 is another flowchart of an embodiment of the nuclear reactor fault early warning method provided in this application;
[0048] Figure 7 is another flowchart of an embodiment of the nuclear reactor fault early warning method provided in this application;
[0049] Figure 8 is a schematic diagram of an embodiment of the nuclear reactor fault early warning system provided in this application;
[0050] Figure 9 is a schematic diagram of the structure of an embodiment of the electronic device provided in this application. Detailed Implementation
[0051] The embodiments of this application are described in detail below. Examples of these embodiments are shown in the accompanying drawings, wherein the same or similar reference numerals denote the same or similar elements or elements having the same or similar functions throughout. The embodiments described below with reference to the accompanying drawings are exemplary and are only used to explain this application, and should not be construed as limiting this application.
[0052] In the description of this application, the use of terms such as "first," "second," etc., is for the purpose of distinguishing technical features only and should not be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated or the order of the technical features indicated.
[0053] In the description of this application, it should be understood that the orientation descriptions, such as up, down, etc., are based on the orientation or positional relationship shown in the accompanying drawings, and are only for the convenience of describing this application and simplifying the description, and do not indicate or imply that the device or element referred to must have a specific orientation, or be constructed and operated in a specific orientation, and therefore should not be construed as a limitation of this application.
[0054] In the description of this application, it should be noted that, unless otherwise explicitly defined, terms such as "setup," "installation," and "connection" should be interpreted broadly, and those skilled in the art can reasonably determine the specific meaning of the above terms in this application in conjunction with the specific content of the technical solution.
[0055] The safe and stable operation of nuclear power plants is crucial to a nation's energy security and social development. Establishing a scientific, accurate, and reliable nuclear power monitoring and early warning system allows for real-time monitoring of key parameters, identification of potential faults and anomalies, and early warning for corresponding measures. A good monitoring and early warning system can also reduce the probability of accidents, lower the severity of accidents, mitigate the consequences of accidents, and improve emergency response capabilities. Therefore, the construction of nuclear power monitoring and early warning systems is an important component of the construction and operation of nuclear power plants in all countries.
[0056] In related technologies, nuclear power plant monitoring and early warning systems typically compare currently collected monitoring data with preset safety thresholds to determine if there are any anomalies in the nuclear reactor, thereby achieving early warning. However, because the collected monitoring data usually has a lag, early warnings for nuclear reactors are often untimely.
[0057] To address the aforementioned technical deficiencies, embodiments of this application provide a method, system, and device for early warning of nuclear reactor failures.
[0058] Please refer to Figure 1, which is a flowchart illustrating a nuclear reactor fault early warning method according to an embodiment of this application. This method is applied to electronic devices, such as servers. As shown in Figure 1, the nuclear reactor fault early warning method includes:
[0059] Step S101: Obtain first monitoring data and second monitoring data at the first moment. The first monitoring data is the data monitored by the monitoring components of the nuclear reactor in its operating environment, and the second monitoring data is the monitoring data of the nuclear reactor in the simulation environment.
[0060] Step S102: When the deviation between the first monitoring data and the second monitoring data exceeds the preset threshold range, and it is determined that the monitoring components are normal, the third monitoring data of the nuclear reactor in the simulation environment at the second time point is obtained. The second time point is the time after the first time point.
[0061] Step S103: Based on the third monitoring data, determine the fault information of the nuclear reactor at the second time point. The fault information is used to indicate whether there is a system fault in the nuclear reactor.
[0062] Step S104: If the fault information indicates that there is a system fault in the nuclear reactor, execute the early warning prompt for the nuclear reactor.
[0063] In this embodiment, by acquiring first and second monitoring data at a first moment, where the first monitoring data is data monitored by monitoring components in the nuclear reactor's operating environment and the second monitoring data is monitoring data of the nuclear reactor in a simulated environment; if the deviation between the first and second monitoring data exceeds a preset threshold range and the monitoring components are determined to be normal, third monitoring data of the nuclear reactor in the simulated environment at a second moment, where the second moment is a time after the first moment; based on the third monitoring data, fault information of the nuclear reactor at the second moment is determined, and the fault information is used to indicate whether a system fault exists in the nuclear reactor; if the fault information indicates that a system fault exists in the nuclear reactor, an early warning prompt is executed for the nuclear reactor. Thus, based on the third monitoring data, fault information of the nuclear reactor at the second moment can be determined, thereby enabling real-time analysis of monitoring data, early warning of abnormal situations, and helping operators to promptly identify potential problems.
[0064] In step S101 above, the electronic device acquires first monitoring data and second monitoring data at a first moment. The first monitoring data is the data monitored by the monitoring components of the nuclear reactor in its operating environment, and the second monitoring data is the monitoring data of the nuclear reactor in a simulated environment.
[0065] The aforementioned first moment could be a single second, a single minute, a single day, or even a time period.
[0066] The aforementioned first monitoring data may include at least one of the system operation data and historical control data of the nuclear reactor in its operating environment at the first moment, which are obtained from the nuclear power plant real-time information monitoring system (KNS) or other monitoring data. The system operation data includes at least one of the production-related operation monitoring data such as reactor core, main loop system, auxiliary system, electrical system, and environmental and process monitoring data.
[0067] The core monitoring parameters include at least one of the following: reactor power, reactor outlet temperature, pressure, flow rate, liquid level, and radiation dose rate. More specifically, the core monitoring parameters include reactor power, reactor outlet temperature, pressure, flow rate, liquid level, and radiation dose rate.
[0068] The main circuit system includes at least one of the following parameters: steam generator water level, temperature, pressure, pressurizer water level or covering gas pressure, flow rate, and main pump speed. More specifically, the main circuit system includes parameters such as steam generator water level, temperature, pressure, pressurizer water level or covering gas pressure, flow rate, and main pump speed.
[0069] An electrical system includes at least one of the following electrical parameters: generator voltage, frequency, active power, reactive power, and power factor. More specifically, an electrical system includes electrical parameters such as generator voltage, frequency, active power, reactive power, and power factor.
[0070] The auxiliary system includes at least one of the following parameters: flow rate, temperature, and pressure of the waste heat extraction system; and pressure, flow rate, and liquid level of the emergency injection system. More specifically, the auxiliary system includes the following parameters: flow rate, temperature, and pressure of the waste heat extraction system; and pressure, flow rate, and liquid level of the emergency injection system.
[0071] The aforementioned second monitoring data may include at least one of the system operation data and control data of the nuclear reactor in the simulated environment at the first moment.
[0072] The acquisition of the first and second monitoring data at the first moment can be achieved by directly acquiring the first and second monitoring data at the first moment through the Transmission Control Protocol / Internet Protocol (TCP / IP).
[0073] In step S102 above, if the deviation between the first monitoring data and the second monitoring data exceeds a preset threshold range and the monitoring component is determined to be normal, the electronic device acquires the third monitoring data of the nuclear reactor in the simulated environment at the second time point, where the second time point is the time after the first time point.
[0074] The aforementioned deviation can be the absolute value of the difference between the first monitoring data and the second monitoring data.
[0075] The second moment mentioned above can be several minutes, several days, or any time period.
[0076] The aforementioned third monitoring data may include at least one of the system operation data and control data of the nuclear reactor in the simulated environment at the second time point.
[0077] When the deviation between the first monitoring data and the second monitoring data exceeds a preset threshold range and the monitoring components are determined to be normal, the third monitoring data of the nuclear reactor in the simulation environment at the second time point is obtained. The second time point is the time after the first time point and can be the absolute value of the difference between the first monitoring data and the second monitoring data. When the absolute value exceeds a preset threshold range and the monitoring components are determined to be normal, at least one of the system operation data and control data of the nuclear reactor in the simulation environment at the second time point is obtained. The second time point is the time after the first time point.
[0078] In step S103 above, the electronic equipment determines the fault information of the nuclear reactor at the second time based on the third monitoring data. The fault information is used to indicate whether there is a system fault in the nuclear reactor.
[0079] The aforementioned fault information may include information indicating that a system fault exists in the nuclear reactor, or information indicating that no system fault exists in the nuclear reactor.
[0080] The aforementioned system failures can refer to a decrease in the performance or loss of function of components or subsystems, which may be caused by wear, aging, or external factors such as impact and corrosion. System failures require immediate diagnosis and repair to prevent further damage to the system.
[0081] Based on the third monitoring data, the above-mentioned fault information of the nuclear reactor at the second time moment is determined. The fault information is used to indicate whether there is a system fault in the nuclear reactor. When the third monitoring data is greater than the preset safety threshold, it is determined that there is a system fault in the nuclear reactor at the second time moment. When the third monitoring data is less than or equal to the preset safety threshold, it is determined that there is no system fault in the nuclear reactor at the second time moment.
[0082] In step S104 above, when the fault information indicates that there is a system fault in the nuclear reactor, the electronic equipment executes a warning prompt for the nuclear reactor.
[0083] The aforementioned warnings can be issued by displaying text messages or by issuing alarm sounds.
[0084] When the fault information indicates that there is a system fault in the nuclear reactor, the early warning prompt for the nuclear reactor can be issued by sending an SMS to a pre-set corresponding client, or by issuing an early warning prompt through a system alarm sound.
[0085] In some embodiments, referring to FIG2, after determining the nuclear reactor fault information at the second time moment based on the third monitoring data in step S103, the method may further include:
[0086] Step S201: When the fault information indicates that there is a system fault in the nuclear reactor, the fault location of the nuclear reactor is performed based on the third monitoring data to determine the faulty component of the nuclear reactor.
[0087] Step S202: Correct the control parameters of the faulty components of the nuclear reactor in a simulated environment to obtain corrected control parameters. Under the corrected control parameters, no system faults occurred in the nuclear reactor in the simulated environment.
[0088] Step S203: Output corrected control parameters;
[0089] Step S204: Based on the modified control parameters, modify the control parameters of the nuclear reactor in the operating environment.
[0090] In this embodiment, the faulty components of the nuclear reactor are identified based on third-party monitoring data, and the control parameters of the faulty components are simulated and corrected in a simulated environment, thereby improving the accuracy and efficiency of fault location and repair.
[0091] The aforementioned faulty components include, but are not limited to, the cooling system, the control system, and the protection system.
[0092] In the case where fault information indicates a system fault in the nuclear reactor, the above-mentioned fault location and fault component determination of the nuclear reactor can be based on third monitoring data. This can be achieved by calculating the deviation between the third monitoring data and the preset safety threshold when the third monitoring data exceeds the preset safety threshold, and then locating the fault in the nuclear reactor and determining the fault component based on the deviation between the third monitoring data and the preset safety threshold.
[0093] The above-mentioned correction of the control parameters of the faulty components of the nuclear reactor in a simulated environment to obtain the corrected control parameters can be achieved by correcting the control parameters of the faulty components of the nuclear reactor in a simulated environment according to a certain rule, judging whether the monitoring data after correction is abnormal after each correction, and stopping the adjustment when the monitoring data is normal, and using the parameter at the time of stopping as the corrected control parameter; or by simultaneously adjusting multiple sets of adjustment parameters of the control parameters of the faulty components of the nuclear reactor in a simulated environment, selecting the set of parameters whose monitoring data is normal after adjustment, and using the set of parameters whose monitoring data is normal after adjustment as the corrected control parameter.
[0094] The above-mentioned output correction control parameters can be output in the form of text or in the form of a pop-up window.
[0095] The aforementioned modification of the control parameters of the nuclear reactor in the operating environment can be done by simultaneously modifying all control parameters corresponding to the modified control parameters of the nuclear reactor in the operating environment; or by dividing all control parameters corresponding to the modified control parameters of the nuclear reactor in the operating environment into several groups and modifying them in batches according to the groups.
[0096] In some embodiments, referring to FIG3, in step S201, based on the third monitoring data, fault location of the nuclear reactor is performed to determine the faulty component of the nuclear reactor, which may include:
[0097] Step S301: If the third monitoring data exceeds the preset safety threshold, calculate the deviation between the third monitoring data and the preset safety threshold;
[0098] Step S302: Based on the deviation between the third monitoring data and the preset safety threshold, identify the faulty component of the nuclear reactor and execute the early warning prompt for the nuclear reactor.
[0099] In this embodiment, the faulty components of the nuclear reactor are identified based on the deviation between third monitoring data and preset safety thresholds, enabling timely prediction of abnormal situations and helping operators to promptly identify potential problems.
[0100] The deviation between the calculated third monitoring data and the preset safety threshold can be the absolute value of the difference between the calculated third monitoring data and the preset safety threshold.
[0101] The above-mentioned method of determining the faulty component of the nuclear reactor and issuing an early warning based on the deviation between the third monitoring data and the preset safety threshold can be achieved by calculating the absolute value of the difference between the third monitoring data and the preset safety threshold, and then using a trained fault diagnosis model to locate the fault in the nuclear reactor and determine the faulty component.
[0102] In some embodiments, referring to FIG4, in step S102, if the deviation between the first monitoring data and the second monitoring data exceeds a preset threshold range and it is determined that the monitoring components are normal, third monitoring data of the nuclear reactor in the simulated environment at a second time point is acquired. The second time point is a time point after the first time point and may include:
[0103] Step S401: If the deviation between the first monitoring data and the second monitoring data exceeds a preset threshold range, perform a validity test on the first monitoring data to determine whether the first monitoring data is valid data.
[0104] Step S402: If the first monitoring data is determined to be valid, obtain the third monitoring data of the nuclear reactor in the simulation environment at the second time point, where the second time point is the time after the first time point.
[0105] In this embodiment, by performing validity checks on the first monitoring data, operators can focus more on the truly important alarm information, improve the accuracy of judging abnormal situations, and reduce false alarms, which helps maintain the stability and reliability of the system and ensures the validity of alarm signals.
[0106] The above-mentioned validity test of the first monitoring data to determine whether the first monitoring data is valid can be based on the first monitoring data to determine whether there is a distorted signal or a pulse signal in the signal of the monitoring component, or it can be based on whether the target indicators of the first monitoring data are abnormal. The target indicators are used to measure at least one of the stability and repeatability of the data. Alternatively, it can be based on the first monitoring data to determine whether there is a distorted signal or a pulse signal in the signal of the monitoring component while simultaneously calculating whether the target indicators of the first monitoring data are abnormal. The target indicators are used to measure at least one of the stability and repeatability of the data.
[0107] The above-mentioned method, assuming the first monitoring data is valid, acquires the third monitoring data of the nuclear reactor in the simulated environment at the second time point. The second time point is the time after the first time point. This can be based on the first monitoring data, assuming the monitoring component signals are free of distortion and pulse signals, and the third monitoring data of the nuclear reactor in the simulated environment at the second time point is acquired. Alternatively, it can be based on the first monitoring data, assuming the target indicators of the first monitoring data are not abnormal, and the third monitoring data of the nuclear reactor in the simulated environment at the second time point is acquired. The second time point is the time after the first time point. Or, it can be based on the first monitoring data, assuming the monitoring component signals are free of distortion and pulse signals and the target indicators of the first monitoring data are not abnormal, and the third monitoring data of the nuclear reactor in the simulated environment at the second time point is acquired. The second time point is the time after the first time point.
[0108] In some embodiments, referring to FIG5, step S401, performing validity testing on the first monitoring data, may include at least one of the following:
[0109] Step S501: Based on the first monitoring data, determine whether there is a distorted signal or a pulse signal in the signal of the monitoring component;
[0110] Step S502: Analyze whether the target indicators of the first monitoring data are abnormal. The target indicators are used to measure at least one of the stability and repeatability of the data.
[0111] In this embodiment, the accuracy of judging abnormal situations is improved and false alarms are reduced by performing validity checks on the first monitoring data.
[0112] The above-mentioned determination of whether the signal of the monitoring component has a distorted signal or a pulse signal based on the first monitoring data can be performed by filtering the first monitoring data value, preprocessing the filtered data value, and determining whether the preprocessed data value has a distorted signal or a pulse signal.
[0113] The above-mentioned statistical analysis of whether the target indicators of the first monitoring data are abnormal, the target indicators used to measure the stability and repeatability of the data, at least one of which can be data filtering of the first monitoring data value, preprocessing of the filtered data value, and determining whether at least one of the stability and repeatability of the preprocessed data value is abnormal.
[0114] In some embodiments, referring to FIG6, after determining whether the first monitoring data is valid data in step S401, the method may further include:
[0115] Step S601: If the first monitoring data is determined to be invalid, determine whether there is a transient anomaly in the first monitoring data. A transient anomaly is at least one of the following: the first monitoring data has a momentary fluctuation or jump signal.
[0116] Step S602: If it is determined that there is no transient abnormality in the first monitoring data, the nuclear reactor is located based on the first monitoring data, the faulty component of the nuclear reactor is identified, and the early warning prompt of the nuclear reactor is executed.
[0117] In this embodiment, by determining that there are no transient anomalies in the first monitoring data, fault location of the nuclear reactor is performed based on the first monitoring data, thereby reducing false alarms.
[0118] The above-mentioned fault location of the nuclear reactor based on the first monitoring data, the identification of the faulty component of the nuclear reactor, and the execution of early warning prompts for the nuclear reactor can be achieved by calculating the deviation between the first monitoring data and the second monitoring data, and using a trained fault diagnosis model based on the deviation between the first monitoring data and the second monitoring data to locate the fault in the nuclear reactor, identify the faulty component of the nuclear reactor, and execute early warning prompts for the nuclear reactor.
[0119] In some implementations, referring to FIG7, the method may further include:
[0120] Step S701: Based on the first monitoring data and the second monitoring data, calculate the indicator parameter values of the target evaluation indicators. The target evaluation indicators include at least one of the MAD value and the MSE value.
[0121] Step S702: Based on the second monitoring data and the preset threshold range, calculate the range of indicator parameters for the target evaluation index;
[0122] Step S703: Based on the index parameter values and index parameter ranges, determine the abnormal system status of the nuclear reactor;
[0123] Step S704: If it is determined that there is a system status anomaly in the nuclear reactor, execute the nuclear reactor status anomaly prompt.
[0124] In this embodiment, the nuclear reactor system status anomalies are determined by the indicator parameter values and ranges of the target evaluation indicators, thereby analyzing and monitoring data in real time, providing alerts for nuclear reactor status anomalies, and helping operators to promptly identify potential problems.
[0125] The aforementioned system status anomaly can be a deviation of the system's operating state from the normal range. However, this deviation may be temporary or non-critical and may not necessarily lead to system shutdown or damage. System status anomaly can be an early sign of failure, requiring further monitoring and analysis to determine whether it will develop into a failure.
[0126] When the above target evaluation indicators include the MSE value, the indicator parameter values of the target evaluation indicators calculated based on the first monitoring data and the second monitoring data can be obtained by the following formula (1):
[0127] In the above formula (1), MSE is the MSE value, Y i The first monitoring data value, y i is the second monitoring data value, and n is the total number of second monitoring data values.
[0128] When the above target evaluation indicators include the MAD value, the indicator parameter values of the target evaluation indicators calculated based on the first monitoring data and the second monitoring data can be obtained by the following formula (2):
[0129] In formula (2) above, MAD is the MAD value, Y i The first monitoring data value, y i is the second monitoring data value, and n is the total number of second monitoring data values.
[0130] When the above target evaluation indicators include the MSE value, the range of indicator parameters for calculating the target evaluation indicators based on the second monitoring data and the preset threshold range can be obtained by the following formula (3):
[0131] In the above formula (3), MSE max The maximum value of the MSE threshold, MSE min Y is the minimum value of the MSE threshold. i,max Y is the maximum value of the preset safety threshold. i,min This is the minimum value of the preset safety threshold;
[0132] When the above target evaluation indicators include the MAD value, the range of indicator parameters for calculating the target evaluation indicators based on the second monitoring data and the preset threshold range can be obtained by the following formula (4):
[0133] In the above formula (4), MAD max The maximum value of the MAD threshold, MAD min Y is the minimum value of the MAD threshold. i,max Y is the maximum value of the preset safety threshold. i,min This is the minimum value of the preset safety threshold.
[0134] The above-mentioned action of issuing a nuclear reactor status anomaly alert when a system status anomaly is determined to exist in the nuclear reactor can be as follows: if the target assessment indicator includes the MSE value, when the MSE value exceeds the MSE threshold range, status anomaly information is generated and the first monitoring data is displayed; or if the target assessment indicator includes the MAD value, when the MAD value exceeds the MAD threshold range, status anomaly information is generated and the first monitoring data is displayed.
[0135] To facilitate understanding by those skilled in the art, the following set of preferred embodiments is provided:
[0136] I. Data Acquisition:
[0137] Acquire first and second monitoring data at a first moment. The first monitoring data is the data monitored by the monitoring components of the nuclear reactor in its operating environment, and the second monitoring data is the monitoring data of the nuclear reactor in a simulated environment.
[0138] II. Second Data Acquisition:
[0139] If the deviation between the first monitoring data and the second monitoring data exceeds a preset threshold range, a validity check is performed on the first monitoring data to determine whether the first monitoring data is valid. The validity check of the first monitoring data includes:
[0140] Based on the first monitoring data, determine whether there are distorted or pulsed signals in the signal of the monitoring component;
[0141] The first monitoring data is used to determine whether the target indicators are abnormal. The target indicators are used to measure at least one of the data's stability and repeatability.
[0142] If the first monitoring data is determined to be valid, the third monitoring data of the nuclear reactor in the simulated environment is obtained at the second time point, which is the time after the first time point.
[0143] III. System Fault Prompt Scenario 1:
[0144] If the first monitoring data is determined to be invalid, determine whether there is a transient anomaly in the first monitoring data. A transient anomaly is defined as at least one of the following: the first monitoring data has a transient fluctuation or jump signal.
[0145] If it is determined that there are no transient anomalies in the first monitoring data, the nuclear reactor is located based on the first monitoring data, the faulty component of the nuclear reactor is identified, and an early warning prompt is issued for the nuclear reactor.
[0146] IV. System Fault Prompt Scenario 2:
[0147] Based on the third monitoring data, fault information of the nuclear reactor at the second time point is determined. This fault information indicates whether a system fault exists in the nuclear reactor. If the fault information indicates a system fault, an early warning notification is issued for the nuclear reactor, specifically as follows:
[0148] If the third monitoring data exceeds the preset safety threshold, calculate the deviation between the third monitoring data and the preset safety threshold;
[0149] Based on the deviation between the third monitoring data and the preset safety threshold, the faulty component of the nuclear reactor is identified and an early warning system for the nuclear reactor is activated.
[0150] V. Status Anomaly Message:
[0151] Based on the first monitoring data and the second monitoring data, the indicator parameter values of the target evaluation indicators are calculated. The target evaluation indicators include at least one of the MAD value and the MSE value.
[0152] Based on the second monitoring data and the preset threshold range, calculate the range of indicator parameters for the target evaluation index;
[0153] Based on the index parameter values and index parameter ranges, the system state anomaly determination of the nuclear reactor is carried out;
[0154] If an abnormality is detected in the nuclear reactor system, a nuclear reactor abnormality notification will be issued.
[0155] VI. Control Parameter Correction:
[0156] When fault information indicates that there is a system fault in the nuclear reactor, the fault location of the nuclear reactor is determined based on third-party monitoring data, and the faulty component of the nuclear reactor is identified.
[0157] The control parameters of the faulty components of the nuclear reactor were corrected in a simulated environment to obtain corrected control parameters. Under the corrected control parameters, no system failure occurred in the nuclear reactor in the simulated environment.
[0158] Output correction control parameters;
[0159] Based on the modified control parameters, the control parameters of the nuclear reactor in the operating environment are modified.
[0160] Additionally, referring to Figure 8, one embodiment of this application provides a fault early warning system for a nuclear reactor, including a first data acquisition module 801, a second data acquisition module 802, a fault determination module 803, and an early warning module 804, wherein:
[0161] The first data acquisition module 801 is used to acquire first monitoring data and second monitoring data at a first moment. The first monitoring data is the data monitored by the monitoring components of the nuclear reactor in its operating environment, and the second monitoring data is the monitoring data of the nuclear reactor in the simulation environment.
[0162] The second data acquisition module 802 is used to acquire the third monitoring data of the nuclear reactor in the simulation environment at a second moment when the deviation between the first monitoring data and the second monitoring data exceeds a preset threshold range and the monitoring components are determined to be normal. The second moment is the moment after the first moment.
[0163] The fault determination module 803 is used to determine the fault information of the nuclear reactor at the second moment based on the third monitoring data. The fault information is used to indicate whether there is a system fault in the nuclear reactor.
[0164] The early warning module 804 is used to issue early warnings for the nuclear reactor when the fault information indicates that there is a system fault in the nuclear reactor.
[0165] In some implementations, the nuclear reactor fault warning system also includes a parameter correction module 805, specifically used for:
[0166] When fault information indicates that there is a system fault in the nuclear reactor, the fault location of the nuclear reactor is determined based on third-party monitoring data, and the faulty component of the nuclear reactor is identified.
[0167] The control parameters of the faulty components of the nuclear reactor were corrected in a simulated environment to obtain corrected control parameters. Under the corrected control parameters, no system failure occurred in the nuclear reactor in the simulated environment.
[0168] Output correction control parameters;
[0169] Based on the modified control parameters, the control parameters of the nuclear reactor in the operating environment are modified.
[0170] In some implementations, the parameter correction module is also specifically used for:
[0171] If the third monitoring data exceeds the preset safety threshold, calculate the deviation between the third monitoring data and the preset safety threshold;
[0172] Based on the deviation between the third monitoring data and the preset safety threshold, the faulty component of the nuclear reactor is identified and an early warning system for the nuclear reactor is activated.
[0173] In some implementations, the second data acquisition module is specifically used for:
[0174] If the deviation between the first monitoring data and the second monitoring data exceeds a preset threshold range, the validity of the first monitoring data is checked to determine whether the first monitoring data is valid.
[0175] If the first monitoring data is determined to be valid, the third monitoring data of the nuclear reactor in the simulated environment is obtained at the second time point, which is the time after the first time point.
[0176] In some implementations, the second data acquisition module is further specifically used for:
[0177] Based on the first monitoring data, determine whether there are distorted or pulsed signals in the signal of the monitoring component;
[0178] The first monitoring data is used to determine whether the target indicators are abnormal. The target indicators are used to measure at least one of the data's stability and repeatability.
[0179] In some implementations, the second data acquisition module is further specifically used for:
[0180] If the first monitoring data is determined to be invalid, determine whether there is a transient anomaly in the first monitoring data. A transient anomaly is defined as at least one of the following: the first monitoring data has a transient fluctuation or jump signal.
[0181] If it is determined that there are no transient anomalies in the first monitoring data, the nuclear reactor is located based on the first monitoring data, the faulty component of the nuclear reactor is identified, and an early warning prompt is issued for the nuclear reactor.
[0182] In some implementations, the nuclear reactor fault early warning system further includes a state anomaly determination module 806, specifically used for:
[0183] Based on the first monitoring data and the second monitoring data, the indicator parameter values of the target evaluation indicators are calculated. The target evaluation indicators include at least one of the MAD value and the MSE value.
[0184] Based on the second monitoring data and the preset threshold range, calculate the range of indicator parameters for the target evaluation index;
[0185] Based on the index parameter values and index parameter ranges, the system state anomaly determination of the nuclear reactor is carried out;
[0186] If an abnormality is detected in the nuclear reactor system, a nuclear reactor abnormality notification will be issued.
[0187] It should be noted that the system embodiments described above are based on the same inventive concept as the method embodiments described above. Therefore, the relevant content of the method embodiments described above is also applicable to the system embodiments described above, and will not be repeated here.
[0188] Figure 9 shows a schematic diagram of the hardware structure for fault early warning of a nuclear reactor provided in an embodiment of this application.
[0189] Fault warning devices in a nuclear reactor may include a processor 901 and a memory 902 storing computer program instructions.
[0190] Specifically, the processor 901 may include a central processing unit (CPU), an application-specific integrated circuit (ASIC), or one or more integrated circuits that can be configured to implement the embodiments of this application.
[0191] Memory 902 may include mass storage for data or instructions. For example, and not limitingly, memory 902 may include a hard disk drive (HDD), floppy disk drive, flash memory, optical disk, magneto-optical disk, magnetic tape, or Universal Serial Bus (USB) drive, or a combination of two or more of these. Where appropriate, memory 902 may include removable or non-removable (or fixed) media. Where appropriate, memory 902 may be internal or external to the integrated gateway disaster recovery device. In a particular embodiment, memory 902 is non-volatile solid-state memory.
[0192] In some embodiments, memory 902 may include read-only memory (ROM), random access memory (RAM), disk storage media device, optical storage media device, flash memory device, electrical, optical, or other physical / tangible memory storage device. Thus, generally, memory includes one or more tangible (non-transitory) computer-readable storage media (e.g., memory devices) encoded with software including computer-executable instructions, and when the software is executed (e.g., by one or more processors), it is operable to perform the operations described with reference to the method according to one aspect of this application.
[0193] The processor 901 reads and executes computer program instructions stored in the memory 902 to implement any of the nuclear reactor fault early warning methods in the above embodiments.
[0194] In one example, the fault warning device for a nuclear reactor may also include a communication interface 903 and a bus 910. As shown in Figure 9, the processor 901, memory 902, and communication interface 903 are connected via the bus 910 and communicate with each other.
[0195] The communication interface 903 is mainly used to realize communication between various modules, devices, units and / or equipment in the embodiments of this application.
[0196] Bus 910 includes hardware, software, or both, that couples components of a nuclear reactor's fault warning device together. For example, and not limitingly, the bus may include an Accelerated Graphics Port (AGP) or other graphics bus, an Enhanced Industry Standard Architecture (EISA) bus, a Front Side Bus (FSB), HyperTransport (HT) interconnect, an Industry Standard Architecture (ISA) bus, an Infinite Bandwidth Interconnect, a Low Pin Count (LPC) bus, a memory bus, a Microchannel Architecture (MCA) bus, a Peripheral Component Interconnect (PCI) bus, a PCI-Express (PCI-X) bus, a Serial Advanced Technology Attachment (SATA) bus, a Video Electronics Standards Association Local (VLB) bus, or other suitable buses, or combinations of two or more of these. Where appropriate, bus 910 may include one or more buses. Although specific buses are described and illustrated in embodiments of this application, any suitable bus or interconnect is contemplated herein.
[0197] The nuclear reactor fault early warning device can execute the nuclear reactor fault early warning method in the embodiments of this application based on a three-dimensional design model, thereby realizing the nuclear reactor fault early warning method and system described in conjunction with Figures 1 and 8.
[0198] Furthermore, in conjunction with the nuclear reactor fault early warning method in the above embodiments, this application embodiment can provide a computer storage medium for implementation. The computer storage medium stores computer program instructions; when these computer program instructions are executed by a processor, they implement any of the nuclear reactor fault early warning methods in the above embodiments.
[0199] It should be clarified that this application is not limited to the specific configurations and processes described above and shown in the figures. For the sake of brevity, detailed descriptions of known methods are omitted here. In the above embodiments, several specific steps are described and shown as examples. However, the method process of this application is not limited to the specific steps described and shown. Those skilled in the art can make various changes, modifications, and additions, or change the order of steps, after understanding the spirit of this application.
[0200] The functional blocks shown in the above-described structural diagram can be implemented as hardware, software, firmware, or a combination thereof. When implemented in hardware, they can be, for example, electronic circuits, application-specific integrated circuits (ASICs), appropriate firmware, plug-ins, function cards, etc. When implemented in software, the elements of this application are programs or code segments used to perform the required tasks. Programs or code segments can be stored on a machine-readable medium or transmitted over a transmission medium or communication link via data signals carried on a carrier wave. "Machine-readable medium" can include any medium capable of storing or transmitting information. Examples of machine-readable media include electronic circuits, semiconductor memory devices, ROM, flash memory, erasable ROM (EROM), floppy disks, CD-ROMs, optical disks, hard disks, fiber optic media, radio frequency (RF) links, etc. Code segments can be downloaded via computer networks such as the Internet, intranets, etc.
[0201] It should also be noted that the exemplary embodiments mentioned in this application describe methods or systems based on a series of steps or apparatus. However, this application is not limited to the order of the above steps; that is, the steps can be performed in the order mentioned in the embodiments, or in a different order, or several steps can be performed simultaneously.
[0202] The aspects of this application have been described above with reference to flowchart illustrations and / or block diagrams of methods, apparatus (systems), and computer program products according to embodiments of this application. It should be understood that each block in the flowchart illustrations and / or block diagrams, and combinations of blocks in the flowchart illustrations and / or block diagrams, can be implemented by computer program instructions. These computer program instructions can be provided to a processor of a general-purpose computer, a special-purpose computer, or other programmable data processing apparatus to produce a machine such that these instructions, executable via the processor of the computer or other programmable data processing apparatus, enable the implementation of the functions / actions specified in one or more blocks of the flowchart illustrations and / or block diagrams. Such a processor can be, but is not limited to, a general-purpose processor, a special-purpose processor, a special application processor, or a field-programmable logic circuit. It is also understood that each block in the block diagrams and / or flowcharts, and combinations of blocks in the block diagrams and / or flowcharts, can also be implemented by dedicated hardware performing the specified functions or actions, or can be implemented by a combination of dedicated hardware and computer instructions.
[0203] The above description is merely a specific implementation of this application. Those skilled in the art will clearly understand that, for the sake of convenience and brevity, the specific working processes of the systems, modules, and units described above can be referred to the corresponding processes in the foregoing method embodiments, and will not be repeated here. It should be understood that the protection scope of this application is not limited thereto. Any person skilled in the art can easily conceive of various equivalent modifications or substitutions within the technical scope disclosed in this application, and these modifications or substitutions should all be covered within the protection scope of this application.
Claims
1. A method for early warning of nuclear reactor failures, characterized in that, The nuclear reactor fault early warning method includes: Acquire first monitoring data and second monitoring data at a first moment, wherein the first monitoring data is the data monitored by the monitoring components of the nuclear reactor in its operating environment, and the second monitoring data is the monitoring data of the nuclear reactor in a simulated environment; If the deviation between the first monitoring data and the second monitoring data exceeds a preset threshold range, and it is determined that the monitoring component is normal, the third monitoring data of the nuclear reactor in the simulation environment at the second time point is obtained, where the second time point is the time after the first time point; Based on the third monitoring data, fault information of the nuclear reactor at the second time point is determined, and the fault information is used to indicate whether there is a system fault in the nuclear reactor. If the fault information indicates that there is a system fault in the nuclear reactor, an early warning prompt will be issued for the nuclear reactor.
2. The method according to claim 1, characterized in that, After determining the fault information of the nuclear reactor at the second time point based on the third monitoring data, the method further includes: When the fault information indicates that there is a system fault in the nuclear reactor, the fault location of the nuclear reactor is performed based on the third monitoring data to determine the faulty component of the nuclear reactor; The control parameters of the faulty component of the nuclear reactor are corrected under the simulation environment to obtain corrected control parameters. Under the corrected control parameters, the nuclear reactor does not experience system failure under the simulation environment. Output the corrected control parameters; Based on the modified control parameters, the control parameters of the nuclear reactor in the operating environment are modified.
3. The method according to claim 2, characterized in that, The step of locating the fault in the nuclear reactor based on the third monitoring data and identifying the faulty component of the nuclear reactor includes: If the third monitoring data exceeds a preset safety threshold, the deviation between the third monitoring data and the preset safety threshold is calculated. Based on the deviation between the third monitoring data and the preset safety threshold, the faulty component of the nuclear reactor is identified and an early warning notification for the nuclear reactor is issued.
4. The method according to claim 1, characterized in that, When the deviation between the first monitoring data and the second monitoring data exceeds a preset threshold range, and it is determined that the monitoring component is functioning normally, third monitoring data of the nuclear reactor in the simulated environment is acquired at a second time point, where the second time point is a time after the first time point, including: If the deviation between the first monitoring data and the second monitoring data exceeds a preset threshold range, the validity of the first monitoring data is checked to determine whether the first monitoring data is valid. If the first monitoring data is determined to be valid, the third monitoring data of the nuclear reactor in the simulated environment is obtained at a second time point, which is a time point after the first time point.
5. The method according to claim 4, characterized in that, The validity check of the first monitoring data includes at least one of the following: Based on the first monitoring data, determine whether the signal of the monitoring component contains distorted or pulse signals; The target indicator of the first monitoring data is statistically analyzed to determine whether it is abnormal. The target indicator is used to measure at least one of the stability and repeatability of the data.
6. The method according to claim 5, characterized in that, After determining whether the first monitoring data is valid data, the method further includes: If the first monitoring data is determined to be invalid, it is determined whether the first monitoring data has a transient anomaly, wherein the transient anomaly is at least one of the following: the first monitoring data has a momentary fluctuation or jump signal. If it is determined that there are no transient anomalies in the first monitoring data, the nuclear reactor is located based on the first monitoring data, the faulty component of the nuclear reactor is identified, and an early warning prompt is issued for the nuclear reactor.
7. The method according to claim 5, characterized in that, Based on the first monitoring data, determining whether the signal of the monitoring component contains distorted or pulsed signals includes: The first monitoring data value is filtered, and the filtered data value is preprocessed to determine whether there is a distorted signal or a pulse signal in the preprocessed data value.
8. The method according to claim 1, characterized in that, The method further includes: Based on the first monitoring data and the second monitoring data, the indicator parameter values of the target evaluation index are calculated, wherein the target evaluation index includes at least one of the MAD value and the MSE value; Based on the second monitoring data and the preset threshold range, calculate the range of index parameters for the target evaluation index; Based on the values and ranges of the aforementioned indicator parameters, the nuclear reactor system status anomaly is determined. If it is determined that there is a system status anomaly in the nuclear reactor, a status anomaly prompt will be executed for the nuclear reactor.
9. A fault early warning system for a nuclear reactor, characterized in that, The nuclear reactor fault early warning system includes: The first data acquisition module is used to acquire first monitoring data and second monitoring data at a first moment. The first monitoring data is the data monitored by the monitoring components of the nuclear reactor in its operating environment, and the second monitoring data is the monitoring data of the nuclear reactor in a simulated environment. The second data acquisition module is used to acquire third monitoring data of the nuclear reactor in the simulation environment at a second time when the deviation between the first monitoring data and the second monitoring data exceeds a preset threshold range and the monitoring component is determined to be normal; the second time is a time after the first time. The fault determination module is used to determine the fault information of the nuclear reactor at the second time based on the third monitoring data, and the fault information is used to indicate whether there is a system fault in the nuclear reactor; The early warning module is used to issue an early warning notification for the nuclear reactor when the fault information indicates that there is a system fault in the nuclear reactor.
10. A fault early warning device for a nuclear reactor, characterized in that, It includes at least one control processor and a memory for communicatively connecting to the at least one control processor; the memory stores instructions executable by the at least one control processor, which, when executed by the at least one control processor, enable the at least one control processor to perform a nuclear reactor fault early warning method as described in any one of claims 1 to 8.
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