Monitoring method, device, electronic equipment and storage medium for nuclear power valve equipment

Abstract

The present application discloses a method for monitoring nuclear power valve equipment, which includes: determining a first parameter value of the nuclear power valve equipment at a first moment, the first parameter value characterizing the working condition of the nuclear power valve equipment at the first moment, the first moment being the moment when the monitoring result of the nuclear power valve equipment is to be determined; constructing a parameter data matrix according to the first parameter value and the second parameter value of the nuclear power valve equipment at the second moment, the second parameter value characterizing the historical working condition of the nuclear power valve equipment at the second moment, the second moment being a historical moment relative to the first moment; determining a first statistical index of the nuclear power valve equipment by a principal component analysis method based on the parameter data matrix and the first covariance matrix of the first parameter value; determining the monitoring result of the nuclear power valve equipment at the first moment according to the first statistical index. The present application also discloses a monitoring device, electronic device and computer-readable storage medium for nuclear power valve equipment.

Description

Technical Field

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

[0002] Nuclear power has many advantages as an efficient and clean energy source. However, with the occurrence of nuclear accidents, it has repeatedly sounded the alarm for nuclear safety, and also caused the public to have deep concerns about nuclear power safety. This has made nuclear power people realize that nuclear power safety is the cornerstone and top priority of nuclear power development. After decades of development, a series of safety regulations have been proposed for nuclear power to ensure the safe operation of nuclear power.

[0003] Foreign nuclear power systems mostly use the concept of equipment reliability. Risk assessment and fault diagnosis of nuclear power valve equipment are the conditions for ensuring the stable operation of nuclear power systems. On the road of technology transformation and independent research and development of AP1000, fault diagnosis and assessment of nuclear power valve equipment have become a protective technology for the safe development of nuclear power.

[0004] Among them, nuclear power valve equipment generally includes but is not limited to valve equipment used in the nuclear island, conventional island and auxiliary facilities system of nuclear power plants. Nuclear power valve equipment is a medium conveying control equipment in nuclear power plants, which can be connected with other systems in nuclear power plants to achieve cut-off, regulation, diversion, backflow prevention, pressure stabilization, diversion and / or overflow pressure relief, etc.

[0005] In order to ensure the safe and stable operation of nuclear power valve equipment, it is necessary to promptly discover and solve the problems existing in nuclear power valve equipment. To achieve this goal, the commonly used means include monitoring the working conditions of nuclear power valve equipment.

[0006] When monitoring the working condition of nuclear power valve equipment, the related technology calculates a fault monitoring threshold through some historical parameter values ​​of the nuclear power valve equipment, and then compares the fault monitoring threshold with the corresponding parameter value of the nuclear power valve equipment at the monitoring time to determine whether the nuclear power valve equipment has a fault. Among them, the related technology defaults to the fault monitoring threshold not changing during the monitoring process.

[0007] However, there are uncertainties in the actual monitoring process, and some unexpected situations may occur, resulting in the nuclear power valve equipment to produce parameter values ​​less than or greater than the fault monitoring threshold even if it is in normal operation, resulting in inaccurate monitoring results obtained based on this comparison with the fault detection threshold. Summary of the invention

[0008] The embodiment of the present application provides a monitoring method for nuclear power valve equipment, which is used to solve the problem that the monitoring results of the working conditions of nuclear power valve equipment obtained by using the existing technology are not accurate enough.

[0009] The embodiments of the present application also provide a monitoring device for nuclear power valve equipment, an electronic device, and a computer-readable storage medium.

[0010] The present application embodiment adopts the following technical solutions:

[0011] A monitoring method for nuclear power valve equipment, comprising:

[0012] Determine a first parameter value of the nuclear power valve equipment at a first moment, the first parameter value represents the working condition of the nuclear power valve equipment at the first moment, and the first moment refers to the moment when the monitoring result of the nuclear power valve equipment is to be determined;

[0013] According to the first parameter value and the second parameter value of the nuclear power valve equipment at the second moment, a parameter data matrix is ​​constructed, wherein the second parameter value represents the historical working condition of the nuclear power valve equipment at the second moment, and the second moment is a historical moment relative to the first moment;

[0014] Based on the parameter data matrix and the first covariance matrix of the first parameter value, determining the first statistical index of the nuclear power valve equipment by a principal component analysis method;

[0015] According to the first statistical indicator, the monitoring result of the nuclear power valve equipment at the first moment is determined.

[0016] Optionally, the method further comprises:

[0017] When a change in the first parameter value is detected, determining a second covariance matrix corresponding to the changed first parameter value;

[0018] Iteratively calculating a second statistical indicator matching the second covariance matrix according to the second covariance matrix;

[0019] According to the second statistical indicator, the monitoring result of the nuclear power valve when the first parameter value changes is determined.

[0020] Optionally, a parameter data matrix is ​​constructed according to the first parameter value and the second parameter value of the nuclear power valve device at the second moment, including:

[0021] Fusing the first parameter value and the second parameter value to obtain a fused first parameter value and a fused second parameter value;

[0022] respectively determining a first parameter value vector of the fused first parameter value and a second parameter value vector of the fused second parameter value;

[0023] A parameter data matrix is ​​constructed based on the first parameter value vector and the second parameter value vector.

[0024] Optionally, fusing the first parameter value and the second parameter value to obtain a fused first parameter value and a fused second parameter value includes:

[0025] Establishing a data interface framework according to the first parameter value and the second parameter value;

[0026] Reconstructing the first parameter value and the second parameter value based on the data interface framework to obtain a reconstruction result;

[0027] According to the reconstruction result, state information, time information and space information of the first parameter value and the second parameter value are respectively extracted through the local ontology of the first parameter value and the second parameter value;

[0028] A domain ontology is constructed based on state information, time information, and space information to achieve fusion of the first parameter value and the second parameter value, thereby obtaining a fused first parameter value and a fused second parameter value.

[0029] Optionally, based on the parameter data matrix and the first covariance matrix of the first parameter value, a first statistical indicator of the nuclear power valve equipment is determined by a principal component analysis method, including: decomposing the parameter data matrix by a principal component analysis method to obtain a load matrix and a score matrix of the parameter data matrix; determining the first statistical indicator of the nuclear power valve equipment according to the load matrix, the score matrix and the first covariance matrix.

[0030] Optionally, determining a first statistical indicator of the nuclear power valve equipment according to the load matrix, the score matrix and the first covariance matrix includes:

[0031] According to the first covariance matrix, calculating the inverse of the characteristic matrix of the first covariance matrix;

[0032] Determine the transpose of the parameter data matrix;

[0033] Compute the transpose of the loading matrix;

[0034] The first statistical index of the nuclear power valve equipment is determined according to the inverse of the characteristic matrix of the first covariance matrix, the transposition of the parameter data matrix, and the transposition of the parameter data matrix and the load matrix.

[0035] Optionally, determining the monitoring result of the nuclear power valve equipment according to the first statistical indicator includes: calculating the statistical control limit of the first statistical indicator under a preset confidence level according to the first statistical indicator; and determining the monitoring result of the nuclear power valve equipment according to the first statistical indicator and the statistical control limit.

[0036] Optionally, the method also includes: visually displaying the monitoring results through a preset visualization system; wherein the preset visualization system includes a three-dimensional display layer, and the three-dimensional display layer is used to visualize the operating status and three-dimensional scene of the nuclear power valve equipment according to the monitoring results.

[0037] A monitoring device for nuclear power valve equipment includes a parameter determination module, a matrix construction module, an index determination module and a result determination module, wherein:

[0038] A parameter determination module, used to determine a first parameter value of a nuclear power valve device at a first moment, the first parameter value is used to characterize the working condition of the nuclear power valve device at the first moment, the first moment refers to the moment when the monitoring result of the nuclear power valve device is to be determined;

[0039] A matrix construction module, for constructing a parameter data matrix according to the first parameter value and the second parameter value of the nuclear power valve device at the second moment, wherein the second parameter value represents the historical working condition of the nuclear power valve device at the second moment, and the second moment is a historical moment relative to the first moment;

[0040] An index determination module, used for determining a first statistical index of a nuclear power valve device by a principal component analysis method based on a parameter data matrix and a first covariance matrix of a first parameter value;

[0041] The result determination module is used to determine the monitoring result of the nuclear power valve equipment at a first moment according to the first statistical indicator.

[0042] Optionally, the device is also used for:

[0043] When a change in the first parameter value is detected, determining a second covariance matrix corresponding to the changed first parameter value;

[0044] Iteratively calculating a second statistical indicator matching the second covariance matrix according to the second covariance matrix;

[0045] According to the second statistical indicator, the monitoring result of the nuclear power valve when the first parameter value changes is determined.

[0046] Optionally, a matrix building block comprising:

[0047] A fusion unit, configured to fuse the first parameter value and the second parameter value to obtain a fused first parameter value and a fused second parameter value;

[0048] a determining unit, configured to respectively determine a first parameter value vector of the fused first parameter value and a second parameter value vector of the fused second parameter value;

[0049] A construction unit is used to construct a parameter data matrix according to the first parameter value vector and the second parameter value vector.

[0050] Optionally, a fusion module is used to:

[0051] Establishing a data interface framework according to the first parameter value and the second parameter value;

[0052] Reconstructing the first parameter value and the second parameter value based on the data interface framework to obtain a reconstruction result;

[0053] According to the reconstruction result, state information, time information and space information of the first parameter value and the second parameter value are respectively extracted through the local ontology of the first parameter value and the second parameter value;

[0054] A domain ontology is constructed based on state information, time information, and space information to achieve fusion of the first parameter value and the second parameter value, thereby obtaining a fused first parameter value and a fused second parameter value.

[0055] Optionally, the indicator determination module includes:

[0056] A decomposition unit is used to decompose the parameter data matrix by a principal component analysis method to obtain a load matrix and a score matrix of the parameter data matrix;

[0057] The index determination unit is used to determine the first statistical index of the nuclear power valve equipment according to the load matrix, the score matrix and the first covariance matrix.

[0058] Optionally, the indicator determination unit is used to:

[0059] According to the first covariance matrix, calculating the inverse of the characteristic matrix of the first covariance matrix;

[0060] Determine the transpose of the parameter data matrix;

[0061] Compute the transpose of the loading matrix;

[0062] The first statistical index of the nuclear power valve equipment is determined according to the inverse of the characteristic matrix of the first covariance matrix, the transposition of the parameter data matrix, and the transposition of the parameter data matrix and the load matrix.

[0063] Optionally, the result determination module is used to:

[0064] According to the first statistical indicator, calculating the statistical control limit of the first statistical indicator under a preset confidence level;

[0065] Determine the monitoring results of nuclear power valve equipment based on the first statistical indicator and statistical control limit.

[0066] Optionally, the device further comprises:

[0067] The monitoring results are visualized through the preset visualization system;

[0068] Among them, the preset visualization system includes a three-dimensional display layer, which is used to visualize the operating status and three-dimensional scenes of nuclear power valve equipment according to the monitoring results.

[0069] An electronic device comprises: a memory, a processor and a computer program stored in the memory and executable on the processor, wherein the computer program implements the steps of the monitoring method for nuclear power valve equipment as described above when executed by the processor.

[0070] A computer-readable storage medium, characterized in that a computer program is stored on the computer-readable storage medium, and when the computer program is executed by a processor, the steps of the monitoring method of nuclear power valve equipment as described above are implemented.

[0071] At least one of the above technical solutions adopted in the embodiments of the present application can achieve the following beneficial effects:

[0072] By adopting the method provided in the embodiment of the present application, a parameter data matrix can be constructed according to the first parameter value of the nuclear power valve equipment at the first moment and the second parameter value at the second moment, and then the first statistical index of the nuclear power valve equipment can be determined by the principal component analysis method based on the parameter data matrix and the first covariance matrix of the first parameter value; finally, the monitoring result of the nuclear power valve equipment at the first moment is determined according to the first statistical index, so as to ensure the accuracy of the monitoring result of the nuclear power valve equipment at the first moment. BRIEF DESCRIPTION OF THE DRAWINGS

[0073] The drawings described herein are used to provide a further understanding of the present application and constitute a part of the present application. The illustrative embodiments of the present application and their descriptions are used to explain the present application and do not constitute an improper limitation on the present application. In the drawings:

[0074] Figure 1a A schematic diagram of the implementation flow of a monitoring method for nuclear power valve equipment provided in an embodiment of the present application;

[0075] Figure 1b A schematic diagram of an implementation flow of a method for fusing a first parameter value and a second parameter value provided in an embodiment of the present application;

[0076] Figure 1c A schematic diagram of a process for constructing a parameter data matrix provided in an embodiment of the present application;

[0077] Figure 1d A schematic diagram of the structure of a preset visualization system provided in an embodiment of the present application;

[0078] Figure 2 A specific structural schematic diagram of a monitoring device for nuclear power valve equipment is provided for an embodiment of the present application;

[0079] Figure 3 A schematic diagram of the structure of an electronic device provided in an embodiment of the present application. DETAILED DESCRIPTION

[0080] In order to make the purpose, technical solution and advantages of the present application clearer, the technical solution of the present application will be clearly and completely described below in combination with the specific embodiments of the present application and the corresponding drawings. Obviously, the described embodiments are only part of the embodiments of the present application, not all of the embodiments. Based on the embodiments in the present application, all other embodiments obtained by ordinary technicians in this field without making creative work are within the scope of protection of the present application.

[0081] The technical solutions provided by various embodiments of the present application are described in detail below in conjunction with the accompanying drawings.

[0082] Example 1

[0083] In order to solve the problem that the monitoring results of the working conditions of nuclear power valve equipment obtained in the prior art are not accurate enough, an embodiment of the present application provides a monitoring method for nuclear power valve equipment.

[0084] The execution subject of the method may be various types of computing devices, or an application or application (Application, APP) installed on the computing device. The computing device may be, for example, a user terminal such as a mobile phone, a tablet computer, a smart wearable device, or a server.

[0085] For ease of description, the present application embodiment takes the execution subject of the method as an example of a server to introduce the method. Those skilled in the art can understand that the present application embodiment takes the server as an example to introduce the method, which is only an exemplary description and does not limit the scope of protection of the claims corresponding to the present solution.

[0086] Specifically, the implementation process of the method provided in the embodiment of the present application is as follows: Figure 1a As shown, the following steps are included:

[0087] Step 11, determining a first parameter value of the nuclear power valve equipment at a first moment, wherein the first parameter value represents the working condition of the nuclear power valve equipment at the first moment, and the first moment refers to the moment when the monitoring result of the nuclear power valve equipment is to be determined.

[0088] The first parameter value may be a parameter value of each working stage or working scenario that can characterize the working condition of the nuclear power valve equipment at the first moment, wherein the working stage / scenario may include, for example, the nuclear power plant unit planning stage / scenario, operation stage / scenario, maintenance stage / scenario, and meteorological / environmental monitoring stage / scenario, and the parameter value may include normal parameter values ​​and abnormal parameter values.

[0089] The first moment can also be understood as the current moment. For example, assuming that the current time is 15:30 on March 22, 2022, the first moment can be considered to be 15:30 on March 22, 2022. Correspondingly, using this example, the first parameter value of the nuclear power valve equipment at the first moment is determined, that is, the first parameter value of the nuclear power valve equipment at 15:30 on March 22, 2022 is determined.

[0090] In summary, the first parameter value of the nuclear power valve device at the first moment in the present application can be understood as the parameter value obtained by real-time measurement of the nuclear power valve device.

[0091] Step 12, constructing a parameter data matrix according to the first parameter value and the second parameter value of the nuclear power valve equipment at the second moment, wherein the second parameter value represents the historical working condition of the nuclear power valve equipment at the second moment, and the second moment is a historical moment relative to the first moment.

[0092] The second moment refers to the historical moment relative to the first moment; for example, following the above example, assuming that the first moment is 15:30 on March 22, 2022, then in this application, the historical moments before 15:30 on March 22, 2022, such as 15:29 on March 22, 2022, 15:17 on March 22, 2022, etc., can be referred to as the second moment.

[0093] Correspondingly, the second parameter value at the second moment can be understood as the parameter value of each working stage or working scenario that can characterize the working condition of the nuclear power valve equipment at a historical moment relative to the first moment, wherein the working stage / scenario may include, for example, the nuclear power plant unit planning stage / scenario, operation stage / scenario, maintenance stage / scenario, and meteorological / environmental monitoring stage / scenarios, and the parameter value may include normal parameter values ​​and abnormal parameter values.

[0094] The parameter data matrix may include a first intermediate result after a first parameter value of the nuclear power valve device changes at a first moment and a second intermediate result after a second parameter value changes; wherein the first intermediate result may include a result after a linear combination of the first parameter value and / or a result after a nonlinear combination of the first parameter value. Similarly, the second intermediate result may include a result after a linear combination of the second parameter value and / or a result after a nonlinear combination of the second parameter value.

[0095] In the present application, a parameter data matrix can be constructed according to the first parameter value and the second parameter value through a principal component analysis method.

[0096] Furthermore, considering that the obtained first parameter value and the second parameter value may be multi-source heterogeneous data, that is, the data formats may be different, for example, some parameter values ​​are in data table format, some are in picture format, or some are in document format, the present application may also perform a fusion preprocessing operation of the multi-source heterogeneous data on the first parameter value and the second parameter value before constructing the parameter data matrix according to the first parameter value and the second parameter value.

[0097] In the present application, when performing a fusion operation of multi-source heterogeneous data on a first parameter value and a second parameter value, a data interface framework can be first established based on the first parameter value and the second parameter value, wherein the data interface framework can be, for example, a multi-source heterogeneous data interface framework; then, data of the first parameter value and the second parameter value are reconstructed based on the data interface framework to obtain a reconstruction result; and based on the reconstruction result, the state information, time information and spatial information of the first parameter value and the second parameter value are respectively extracted through the local ontology of the first parameter value and the second parameter value; finally, a domain ontology is constructed based on the state information, time information and spatial information to realize the fusion of the first parameter value and the second parameter value, and obtain a fused first parameter value and a fused second parameter value.

[0098] In practical applications, such as Figure 1b As shown, the data of nuclear power valve equipment in each working stage (operation stage, maintenance stage, meteorological / environmental monitoring stage, and planning stage) can be obtained based on the first parameter value and the second parameter value, and then high-dimensional feature expression information matching the data of each working stage can be reconstructed based on the data of the stage, and then based on the high-dimensional feature expression information, state information, time information, and spatial information can be extracted, and finally, based on the state information, time information, and spatial information, step-by-step element fusion operations and feature center fusion operations are performed to achieve the fusion of the first parameter value and the second parameter value.

[0099] It should be noted that the above-mentioned working stages are merely an exemplary description of the embodiments of the present application and do not impose any limitation on the present application.

[0100] Optional, such as Figure 1c As shown, in one embodiment, the parameter data matrix can be constructed as follows.

[0101] Step 121 , fusing the first parameter value and the second parameter value to obtain a fused first parameter value and a fused second parameter value.

[0102] Among them, the specific implementation method of fusing the first parameter value and the second parameter value can refer to the above-mentioned related content, which will not be repeated here.

[0103] Step 122, respectively determine a first parameter value vector of the fused first parameter value and a second parameter value vector of the fused second parameter value.

[0104] For example, suppose the first parameter value after fusion is x 11 ,x 12 ,…x 1m , then the first parameter value vector is Where m represents the number of continuously acquired time series sampling points.

[0105] The second parameter value vector of the fused second parameter value is composed of the parameter values ​​of the nuclear power valve equipment at each working stage at the second moment. For example, the parameter value of the operating stage in the fused second parameter value is x 21 ,x 22 ,…x 2m , then the parameter vector of the running phase is The parameter value of the maintenance phase in the second parameter value after fusion is x 31 ,x 32 ,…x 3m , then the parameter vector of the maintenance phase is Correspondingly, for the parameter value x of stage i in the second parameter value after fusion i1 ,x i2 ,…x im , we can determine the parameter vector of stage i as The i stage may be, for example, a meteorological / environmental monitoring stage or a planning stage.

[0106] Step 123, constructing a parameter data matrix according to the first parameter value vector and the second parameter value vector.

[0107] In the embodiment of the present application, the first parameter value vector and the second parameter value vector can be used to form a parameter data matrix through a principal component analysis method to facilitate subsequent processing.

[0108] For example, using the above example, assume that the first parameter value vector is The second parameter value vector includes Then the following parameter matrix X can be constructed based on the first parameter value vector and the second parameter value vector, where:

[0109]

[0110] Step 13: Based on the parameter data matrix and the first covariance matrix of the first parameter value, determine the first statistical index of the nuclear power valve equipment by using a principal component analysis method.

[0111] In the present application, after executing step 12 to obtain the parameter data matrix, the first statistical index of the nuclear power valve equipment can be further determined based on the parameter data matrix using a principal component analysis method.

[0112] Among them, the first statistical index of nuclear power valve equipment is also called Hotelling's T 2 or T 2 ), which is used to characterize the deviation of the first parameter value from the parameter data matrix in terms of uncertain change trend and change amplitude.

[0113] In the present application, the parameter data matrix can be decomposed by the principal component analysis method to obtain the load matrix and the score matrix of the parameter data matrix; then, the first statistical index of the nuclear power valve equipment is determined according to the load matrix, the score matrix and the first covariance matrix.

[0114] For example, the parameter data matrix can be decomposed according to the following formula (1) using the principal component analysis method.

[0115] X=TP T +E (1)

[0116] Where X represents the parameter data matrix; P represents the load matrix, P T represents the transpose of the loading matrix; T represents the score matrix; E represents the residual error.

[0117] Further, the first covariance matrix of the first parameter value can be determined. And, after obtaining the first covariance matrix, the load matrix, and the score matrix, the inverse of the characteristic matrix of the first covariance matrix can be calculated according to the first covariance matrix; the transpose of the parameter data matrix can be determined; the transpose of the load matrix can be calculated; and the first statistical index of the nuclear power valve equipment can be determined according to the inverse of the characteristic matrix of the first covariance matrix, the transpose of the parameter data matrix, and the transpose of the parameter data matrix and the load matrix.

[0118] In practical applications, for example, the first statistical indicator can be determined according to the following formula (2) based on the inverse of the characteristic matrix of the first covariance matrix, the transpose of the parameter data matrix, and the transpose of the parameter data matrix and the loading matrix.

[0119] T 2 =XPΛ -1 P T X T (2)

[0120] Among them, Λ -1 represents the inverse of the characteristic matrix of the first covariance matrix; X T represents the transpose of the parameter data matrix X.

[0121] Step 14: Determine the monitoring result of the nuclear power valve equipment at the first moment according to the first statistical indicator.

[0122] In the present application, after the first statistical indicator is calculated, the statistical control limit of the statistical indicator under a preset confidence level can be calculated according to the first statistical indicator according to the following formula (3).

[0123]

[0124] in, represents the statistical control limit, k represents the number of principal components, m represents the number of variables in the first parameter value vector, and F(k,mk,α) represents the probability value when the data conforms to the F distribution with the degree of freedom (mk) and the confidence level α, which can be calculated according to the relevant principal component analysis method.

[0125] Then, the monitoring result of the nuclear power valve equipment is determined according to the first statistical index and the statistical control limit.

[0126] In this application, considering that the first parameter value may change with time, the first statistical indicator will be continuously updated, based on which, in order to accurately determine the detection result. In this application, when the first parameter value is monitored to change, the second covariance matrix corresponding to the changed first parameter value can be determined; according to the second covariance matrix, the second statistical indicator matching the second covariance matrix is ​​iteratively calculated; according to the second statistical indicator, the monitoring result of the nuclear power valve when the first parameter value changes is determined.

[0127] The second covariance matrix can be determined according to the following formula (4):

[0128]

[0129] Among them, R l+1 is the covariance matrix of the l+1th group of data, N l is the cumulative sum from 1 to l, It indicates the change in the average value of all new data compared to the average value of the first l groups of data after the l+1th group of new data is added.

[0130] After calculating the second covariance matrix, the number of new principal components, as well as the second statistical indicators and second statistical control limits matching the second covariance matrix can be iteratively calculated according to the iterative principal component analysis method. Then, the monitoring results of the nuclear power valve when the first parameter value changes can be determined according to the second statistical indicators and the second statistical control limits.

[0131] In an optional embodiment, after obtaining the monitoring results, the present application can also visualize the monitoring results through a preset visualization system; wherein the preset visualization system includes a three-dimensional display layer, and the three-dimensional display layer is used to visualize the operating status and three-dimensional scene of the nuclear power valve equipment according to the monitoring results.

[0132] Among them, the preset visualization system uses the nuclear power plant scene as the information carrier, nuclear power units and key equipment as the data organization basis, and is a basic platform for realizing the application and display of visualization technology.

[0133] like Figure 1d As shown, it is a schematic diagram of the structure of a preset visualization system provided in an embodiment of the present application. As can be seen from the figure, the system includes a data storage layer, an interface layer, a computing layer and a three-dimensional display layer; wherein the data storage layer and the interface layer are based on the nuclear power data fusion management platform, and the main data used include historical databases and data files stored on distributed clusters. Furthermore, in order to visualize the three-dimensional environment of a nuclear power plant, in addition to the above-mentioned data files, it can also include structured data of geospatial information databases and related model calculations.

[0134] Secondly, the computing layer and the three-dimensional display layer communicate with each other to jointly display the three-dimensional environment. On the panoramic display interface, OpenLayers supports multiple scene layer sources and supports the superposition of map backgrounds and other layers. Cesium supports the map engine of three-dimensional scenes to realize the visualization of dynamic geographic spatial data. It calculates and displays the three-dimensional models of various components of nuclear power valve equipment (for example, valve bodies, valve stems, controllers, etc.), and combines the obtained monitoring results to complete the visualization of the operating status of nuclear power valve equipment and the three-dimensional scene. Among them, in the computing layer, the query request of the two-dimensional map will be submitted to GeoServer, and the relevant requests in the three-dimensional environment will be processed by the 3DCityDB client.

[0135] By adopting the method provided in the embodiment of the present application, a parameter data matrix is ​​constructed according to the first parameter value of the nuclear power valve equipment at the first moment and the second parameter value at the second moment, and then based on the parameter data matrix and the first covariance matrix of the first parameter value, the first statistical index of the nuclear power valve equipment is determined by the principal component analysis method; finally, according to the first statistical index, the monitoring result of the nuclear power valve equipment at the first moment is determined, so as to ensure the accuracy of the monitoring result of the nuclear power valve equipment at the first moment.

[0136] Example 2

[0137] In order to solve the problem that the monitoring results of the working condition of nuclear power valve equipment obtained by the prior art are not accurate enough, the embodiment of the present application provides a monitoring device for nuclear power valve equipment, and the specific structural diagram of the device is shown as follows: Figure 2 As shown, it includes a parameter determination module 21, a matrix construction module 22, an indicator determination module 23 and a result determination module 24. The functions of each module are as follows:

[0138] The parameter determination module 21 is used to determine a first parameter value of the nuclear power valve equipment at a first moment, the first parameter value is used to characterize the working condition of the nuclear power valve equipment at the first moment, and the first moment refers to the moment when the monitoring result of the nuclear power valve equipment is to be determined.

[0139] The matrix construction module 22 is used to construct a parameter data matrix according to the first parameter value and the second parameter value of the nuclear power valve equipment at the second moment, wherein the second parameter value represents the historical working condition of the nuclear power valve equipment at the second moment, and the second moment is a historical moment relative to the first moment.

[0140] The index determination module 23 is used to determine the first statistical index of the nuclear power valve equipment through the principal component analysis method based on the parameter data matrix and the first covariance matrix of the first parameter value.

[0141] The result determination module 24 is used to determine the monitoring result of the nuclear power valve equipment at the first moment according to the first statistical indicator.

[0142] Optionally, the device is also used for:

[0143] When a change in the first parameter value is detected, determining a second covariance matrix corresponding to the changed first parameter value;

[0144] Iteratively calculating a second statistical indicator matching the second covariance matrix according to the second covariance matrix;

[0145] According to the second statistical indicator, the monitoring result of the nuclear power valve when the first parameter value changes is determined.

[0146] Optionally, a matrix building block comprising:

[0147] A fusion unit, configured to fuse the first parameter value and the second parameter value to obtain a fused first parameter value and a fused second parameter value;

[0148] a determining unit, configured to respectively determine a first parameter value vector of the fused first parameter value and a second parameter value vector of the fused second parameter value;

[0149] A construction unit is used to construct a parameter data matrix according to the first parameter value vector and the second parameter value vector.

[0150] Optionally, a fusion module is used to:

[0151] Establishing a data interface framework according to the first parameter value and the second parameter value;

[0152] Reconstructing the first parameter value and the second parameter value based on the data interface framework to obtain a reconstruction result;

[0153] According to the reconstruction result, state information, time information and space information of the first parameter value and the second parameter value are respectively extracted through the local ontology of the first parameter value and the second parameter value;

[0154] A domain ontology is constructed based on state information, time information, and space information to achieve fusion of the first parameter value and the second parameter value, thereby obtaining a fused first parameter value and a fused second parameter value.

[0155] Optionally, the indicator determination module includes:

[0156] A decomposition unit is used to decompose the parameter data matrix by a principal component analysis method to obtain a load matrix and a score matrix of the parameter data matrix;

[0157] The index determination unit is used to determine the first statistical index of the nuclear power valve equipment according to the load matrix, the score matrix and the first covariance matrix.

[0158] Optionally, the indicator determination unit is used to:

[0159] According to the first covariance matrix, calculating the inverse of the characteristic matrix of the first covariance matrix;

[0160] Determine the transpose of the parameter data matrix;

[0161] Compute the transpose of the loading matrix;

[0162] The first statistical index of the nuclear power valve equipment is determined according to the inverse of the characteristic matrix of the first covariance matrix, the transposition of the parameter data matrix, and the transposition of the parameter data matrix and the load matrix.

[0163] Optionally, the result determination module is used to:

[0164] According to the first statistical indicator, calculating the statistical control limit of the first statistical indicator under a preset confidence level;

[0165] Determine the monitoring results of nuclear power valve equipment based on the first statistical indicator and statistical control limit.

[0166] Optionally, the device further comprises:

[0167] The monitoring results are visualized through the preset visualization system;

[0168] Among them, the preset visualization system includes a three-dimensional display layer, which is used to visualize the operating status and three-dimensional scenes of nuclear power valve equipment according to the monitoring results.

[0169] By using the device provided in the embodiment of the present application, a parameter data matrix can be constructed based on the first parameter value of the nuclear power valve equipment at the first moment and the second parameter value at the second moment, and then the first statistical index of the nuclear power valve equipment can be determined by the principal component analysis method based on the parameter data matrix and the first covariance matrix of the first parameter value; finally, the monitoring result of the nuclear power valve equipment at the first moment is determined based on the first statistical index, so as to ensure the accuracy of the monitoring result of the nuclear power valve equipment at the first moment.

[0170] Example 3

[0171] The present application embodiment relates to an electronic device, such as Figure 3 As shown. At the hardware level, the electronic device includes a processor, and optionally also includes an internal bus, a network interface, and a memory. Among them, the memory may include a memory, such as a high-speed random access memory (RAM), and may also include a non-volatile memory (non-volatile memory), such as at least one disk storage, etc. Of course, the electronic device may also include hardware required for other services.

[0172] The processor, network interface and memory can be interconnected through an internal bus, which can be an ISA (Industry Standard Architecture) bus, a PCI (Peripheral Component Interconnect) bus or an EISA (Extended Industry Standard Architecture) bus, etc. The bus can be divided into an address bus, a data bus, a control bus, etc. For ease of representation, Figure 3 It is represented by only one bidirectional arrow, but it does not mean that there is only one bus or one type of bus.

[0173] The memory is used to store the program. Specifically, the program may include a program code, and the program code includes a computer operation instruction. The memory may include a memory and a non-volatile memory, and provides instructions and data to the processor.

[0174] The processor reads the corresponding computer program from the non-volatile memory into the memory and then runs it, forming a monitoring device for nuclear power valve equipment at the logical level. The processor executes the program stored in the memory and is specifically used to perform the following operations:

[0175] Determine a first parameter value of the nuclear power valve equipment at a first moment, the first parameter value represents the working condition of the nuclear power valve equipment at the first moment, and the first moment refers to the moment when the monitoring result of the nuclear power valve equipment is to be determined;

[0176] According to the first parameter value and the second parameter value of the nuclear power valve equipment at the second moment, a parameter data matrix is ​​constructed, wherein the second parameter value represents the historical working condition of the nuclear power valve equipment at the second moment, and the second moment is a historical moment relative to the first moment;

[0177] Based on the parameter data matrix and the first covariance matrix of the first parameter value, determining the first statistical index of the nuclear power valve equipment by a principal component analysis method;

[0178] According to the first statistical indicator, the monitoring result of the nuclear power valve equipment at the first moment is determined.

[0179] The monitoring method of a nuclear power valve equipment provided in the present specification can be applied to a processor or implemented by a processor. The processor may be an integrated circuit chip with signal processing capabilities. In the implementation process, each step of the above method can be completed by an integrated logic circuit of hardware in the processor or instructions in the form of software. The above processor can be a general-purpose processor, including a central processing unit (CPU), a network processor (NP), etc.; it can also be a digital signal processor (DSP), an application-specific integrated circuit (ASIC), a field-programmable gate array (FPGA) or other programmable logic devices, discrete gates or transistor logic devices, discrete hardware components. The various methods, steps and logic block diagrams disclosed in the embodiments of this specification can be implemented or executed. The general-purpose processor can be a microprocessor or the processor can also be any conventional processor, etc.

[0180] The steps of the method disclosed in the embodiments of this specification can be directly embodied as being executed by a hardware decoding processor, or can be executed by a combination of hardware and software modules in the decoding processor. The software module can be located in a mature storage medium in the art such as a random access memory, a flash memory, a read-only memory, a programmable read-only memory, or an electrically erasable programmable memory, a register, etc. The storage medium is located in a memory, and the processor reads the information in the memory and completes the steps of the above method in combination with its hardware.

[0181] The embodiments of this specification also provide a computer-readable storage medium, which stores one or more programs, and the one or more programs include instructions. When the instructions are executed by an electronic device including multiple application programs, the electronic device can execute a monitoring method for nuclear power valve equipment, and is specifically used to execute:

[0182] Determine a first parameter value of the nuclear power valve equipment at a first moment, the first parameter value represents the working condition of the nuclear power valve equipment at the first moment, and the first moment refers to the moment when the monitoring result of the nuclear power valve equipment is to be determined;

[0183] According to the first parameter value and the second parameter value of the nuclear power valve equipment at the second moment, a parameter data matrix is ​​constructed, wherein the second parameter value represents the historical working condition of the nuclear power valve equipment at the second moment, and the second moment is a historical moment relative to the first moment;

[0184] Based on the parameter data matrix and the first covariance matrix of the first parameter value, determining the first statistical index of the nuclear power valve equipment by a principal component analysis method;

[0185] According to the first statistical indicator, the monitoring result of the nuclear power valve equipment at the first moment is determined.

[0186] The systems, devices, modules or units described in the above embodiments may be implemented by computer chips or entities, or by products with certain functions. A typical implementation device is a computer.

[0187] For the convenience of description, the above device is described in various units according to their functions. Of course, when implementing this specification, the functions of each unit can be implemented in the same or multiple software and / or hardware.

[0188] Those skilled in the art will appreciate that the embodiments of this specification may be provided as methods, devices, or computer program products. Therefore, this specification may take the form of a complete hardware embodiment, a complete software embodiment, or an embodiment combining software and hardware. Moreover, this specification may take the form of a computer program product implemented on one or more computer-usable storage media (including but not limited to disk storage, CD-ROM, optical storage, etc.) containing computer-usable program code.

[0189] This specification is described with reference to the flowchart and / or block diagram of the method, device (system), and computer program product according to the embodiment of this specification. It should be understood that each process and / or box in the flowchart and / or block diagram, as well as the combination of the process and / or box in the flowchart and / or block diagram 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, an embedded processor or other programmable data processing device to produce a machine, so that the instructions executed by the processor of the computer or other programmable data processing device produce a device for implementing the functions specified in one process or multiple processes in the flowchart and / or one box or multiple boxes in the block diagram.

[0190] These computer program instructions may also be stored in a computer-readable memory that can direct a computer or other programmable data processing device to work in a specific manner, so that the instructions stored in the computer-readable memory produce a manufactured product including an instruction device that implements the functions specified in one or more processes in the flowchart and / or one or more boxes in the block diagram.

[0191] These computer program instructions may also be loaded onto a computer or other programmable data processing device so that a series of operational steps are executed on the computer or other programmable device to produce a computer-implemented process, whereby the instructions executed on the computer or other programmable device provide steps for implementing the functions specified in one or more processes in the flowchart and / or one or more boxes in the block diagram.

[0192] In a typical configuration, a computing device includes one or more processors (CPU), input / output interfaces, network interfaces, and memory.

[0193] The memory may include non-permanent storage in a computer-readable medium, random access memory (RAM) and / or non-volatile memory in the form of read-only memory (ROM) or flash RAM. The memory is an example of a computer-readable medium.

[0194] Computer readable media include permanent and non-permanent, removable and non-removable media and can store information by any method or technology. The information can be computer readable instructions, data structures, program modules or other data.

[0195] It should also be noted that the terms "include", "comprises" or any other variations thereof are intended to cover non-exclusive inclusion, so that a process, method, commodity or device including a series of elements includes not only those elements, but also other elements not explicitly listed, or also includes elements inherent to such process, method, commodity or device. In the absence of more restrictions, the elements defined by the sentence "comprises a ..." do not exclude the existence of other identical elements in the process, method, commodity or device including the elements.

[0196] Each embodiment in this specification is described in a progressive manner, and the same or similar parts between the embodiments can be referred to each other, and each embodiment focuses on the differences from other embodiments. In particular, for the system embodiment, since it is basically similar to the method embodiment, the description is relatively simple, and the relevant parts can be referred to the partial description of the method embodiment.

Claims

1. A monitoring method for nuclear power valve equipment, characterized in that: include: Determine a first parameter value of a nuclear power valve device at a first moment, wherein the first parameter value represents a working condition of the nuclear power valve device at the first moment, and the first moment refers to a moment when a monitoring result of the nuclear power valve device is to be determined; Constructing a parameter data matrix according to the first parameter value and a second parameter value of the nuclear power valve device at the second moment, wherein the second parameter value represents the historical working condition of the nuclear power valve device at the second moment, and the second moment is a historical moment relative to the first moment; Based on the parameter data matrix and the first covariance matrix of the first parameter value, determining the first statistical index of the nuclear power valve equipment by a principal component analysis method; Determining the monitoring result of the nuclear power valve equipment at the first moment according to the first statistical indicator; Determining the monitoring result of the nuclear power valve equipment according to the first statistical indicator includes: Calculating a first statistical control limit of the first statistical indicator at a preset confidence level according to the first statistical indicator; Determining the monitoring result of the nuclear power valve equipment according to the first statistical indicator and the first statistical control limit; The method further comprises: When a change in the first parameter value is detected, determining a second covariance matrix corresponding to the changed first parameter value; Iteratively calculating a second statistical indicator matching the second covariance matrix according to the second covariance matrix, and determining a second statistical control limit; The monitoring result of the nuclear power valve when the first parameter value changes is determined according to the second statistical indicator and the second statistical control limit.

2. The method according to claim 1, characterized in that According to the first parameter value and the second parameter value of the nuclear power valve device at the second moment, a parameter data matrix is ​​constructed, including: Fusing the first parameter value and the second parameter value to obtain a fused first parameter value and a fused second parameter value; respectively determining a first parameter value vector of the fused first parameter value and a second parameter value vector of the fused second parameter value; The parameter data matrix is ​​constructed according to the first parameter value vector and the second parameter value vector.

3. The method according to claim 2, characterized in that The method of fusing the first parameter value and the second parameter value to obtain a fused first parameter value and a fused second parameter value includes: Establishing a data interface framework according to the first parameter value and the second parameter value; Reconstructing the first parameter value and the second parameter value based on the data interface framework to obtain a reconstruction result; According to the reconstruction result, extracting state information, time information and space information of the first parameter value and the second parameter value respectively through the local ontology of the first parameter value and the second parameter value; A domain ontology is constructed based on the state information, the time information, and the space information to achieve fusion of the first parameter value and the second parameter value, thereby obtaining the fused first parameter value and the fused second parameter value.

4. The method according to claim 1, characterized in that Based on the parameter data matrix and the first covariance matrix of the first parameter value, determining the first statistical index of the nuclear power valve equipment by a principal component analysis method includes: Decomposing the parameter data matrix by principal component analysis to obtain a load matrix and a score matrix of the parameter data matrix; The first statistical indicator of the nuclear power valve equipment is determined according to the load matrix, the score matrix and the first covariance matrix.

5. The method according to claim 4, characterized in that Determining the first statistical index of the nuclear power valve equipment according to the load matrix, the score matrix and the first covariance matrix includes: Calculating an inverse of a characteristic matrix of the first covariance matrix according to the first covariance matrix; determining the transpose of the parameter data matrix; calculating the transpose of the loading matrix; The first statistical index of the nuclear power valve equipment is determined according to the inverse of the characteristic matrix of the first covariance matrix, the transpose of the parameter data matrix, and the transpose of the parameter data matrix and the load matrix.

6. The method according to claim 1, characterized in that The method further comprises: Visually display the monitoring results through a preset visualization system; Wherein, the preset visualization system includes a three-dimensional display layer, and the three-dimensional display layer is used to visualize the operating status and three-dimensional scene of the nuclear power valve equipment according to the monitoring results.

7. A monitoring device for nuclear power valve equipment, characterized in that: It includes parameter determination module, matrix construction module, indicator determination module and result determination module, among which: A parameter determination module, used to determine a first parameter value of a nuclear power valve device at a first moment, wherein the first parameter value is used to characterize a working condition of the nuclear power valve device at the first moment, and the first moment refers to a moment when a monitoring result of the nuclear power valve device is to be determined; a matrix construction module, configured to construct a parameter data matrix according to the first parameter value and a second parameter value of the nuclear power valve device at a second moment, wherein the second parameter value represents a historical working condition of the nuclear power valve device at the second moment, and the second moment is a historical moment relative to the first moment; An index determination module, used for determining a first statistical index of the nuclear power valve equipment by a principal component analysis method based on the parameter data matrix and a first covariance matrix of the first parameter value; A result determination module, used to determine the monitoring result of the nuclear power valve equipment at the first moment according to the first statistical indicator; In the result determination module, determining the monitoring result of the nuclear power valve equipment according to the first statistical indicator includes: Calculating a first statistical control limit of the first statistical indicator at a preset confidence level according to the first statistical indicator; Determining the monitoring result of the nuclear power valve equipment according to the first statistical indicator and the first statistical control limit; The monitoring device is also used for: When a change in the first parameter value is detected, determining a second covariance matrix corresponding to the changed first parameter value; Iteratively calculating a second statistical indicator matching the second covariance matrix according to the second covariance matrix, and determining a second statistical control limit; The monitoring result of the nuclear power valve when the first parameter value changes is determined according to the second statistical indicator and the second statistical control limit.

8. An electronic device, characterized in that: include: A memory, a processor, and a computer program stored in the memory and executable on the processor, wherein the computer program, when executed by the processor, implements the steps of the method for monitoring nuclear power valve equipment as described in any one of claims 1 to 6.

9. A computer-readable storage medium, characterized in that: The computer-readable storage medium stores a computer program, and when the computer program is executed by a processor, the steps of the method for monitoring nuclear power valve equipment according to any one of claims 1 to 6 are implemented.

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