Nuclear power station refueling machine data processing method, device and equipment and storage medium

Abstract

The invention provides a nuclear power station refueling machine data processing method and device, equipment and a storage medium. The nuclear power station refueling machine data processing method comprises the steps of obtaining first load data corresponding to a target load operation in a nuclear power station refueling machine in response to the target load operation in the nuclear power station refueling machine; determining a data acquisition period, and obtaining second load data in a target load operation execution process in the nuclear power station refueling machine based on the data acquisition period; acquiring historical load data of historical load operation corresponding to the target load operation; and performing mechanical analysis on the target load operation based on the first load data, the second load data and the historical load data. According to the embodiment of the invention, the accuracy of safety analysis based on the collected load information can be improved.

Description

Technical Field

[0001] The present disclosure relates to the field of nuclear power, and particularly to a method, apparatus, device, and storage medium for processing data of a refueling machine in a nuclear power plant. Background Art

[0002] The refueling machine of a pressurized water reactor nuclear power plant is a key device for loading and unloading nuclear fuel in the nuclear power plant, and its function is to transport fuel assemblies between the reactor core and the transfer system. The safe operation of the refueling machine will affect the safety of the entire pressurized water reactor nuclear power plant. Therefore, in order to ensure the safe operation of the refueling machine, it is necessary to collect the load data in the refueling machine for data analysis to realize the safety analysis of the operating environment of the refueling machine. This process is crucial for the safe operation and economy of the nuclear power plant.

[0003] However, in the related art, the accuracy of safety analysis based on the collected load information is relatively low. Summary of the Invention

[0004] Embodiments of the present disclosure provide a method, apparatus, device, and storage medium for processing data of a refueling machine in a nuclear power plant, which can improve the accuracy of safety analysis based on the collected load information.

[0005] According to one aspect of the present disclosure, there is provided a method for processing data of a refueling machine in a nuclear power plant, including:

[0006] In response to a target load operation in a refueling machine of a nuclear power plant, obtaining first load data corresponding to the target load operation from the refueling machine of the nuclear power plant, where the first load data is collected by a controller in the refueling machine of the nuclear power plant from multiple data dimensions;

[0007] Determining a data collection period, and obtaining second load data during the execution of the target load operation in the refueling machine of the nuclear power plant based on the data collection period;

[0008] Obtaining historical load data of a historical load operation corresponding to the target load operation;

[0009] Performing a mechanical analysis on the target load operation based on the first load data, the second load data, and the historical load data.

[0010] According to one aspect of the present disclosure, there is provided a device for processing data of a refueling machine in a nuclear power plant, including:

[0011] A first obtaining unit, configured to obtain first load data corresponding to a target load operation from a refueling machine of a nuclear power plant in response to the target load operation in the refueling machine of the nuclear power plant, where the first load data is collected by a controller in the refueling machine of the nuclear power plant from multiple data dimensions;

[0012] A second acquisition unit, configured to determine a data acquisition period, and acquire second load data during the execution of the target load operation in the nuclear power plant refueling machine based on the data acquisition period;

[0013] A third acquisition unit, configured to acquire historical load data of a historical load operation corresponding to the target load operation;

[0014] A mechanical analysis unit, configured to perform a mechanical analysis on the target load operation based on the first load data, the second load data, and the historical load data.

[0015] Optionally, the mechanical analysis unit is specifically configured to:

[0016] Construct load trend data based on the first load data, the second load data, and the historical load data;

[0017] Perform a mechanical analysis on the target load operation based on the load trend data.

[0018] Optionally, the mechanical analysis unit is specifically configured to:

[0019] For multiple data dimensions, acquire first sub-load data, second sub-load data, and historical sub-load data corresponding to each data dimension from the first load data, the second load data, and the historical load data;

[0020] Construct load trend data corresponding to each data dimension based on the first sub-load data, the second sub-load data, and the historical sub-load data corresponding to each data dimension.

[0021] Optionally, the nuclear power plant refueling machine data processing device further includes:

[0022] A first determination unit, configured to determine a data recording period;

[0023] A storage unit, configured to store the first load data and the second load data in a load information database based on the data recording period.

[0024] Optionally, the nuclear power plant refueling machine data processing device further includes:

[0025] A fourth acquisition unit, configured to acquire third load data corresponding to the overload / underload fault warning when receiving an overload / underload fault warning between a first nuclear fuel assembly and a second nuclear fuel assembly in the nuclear power plant refueling machine during the execution of the target load operation;

[0026] A second determination unit, configured to determine the hooking state of the grid bars between the first nuclear fuel assembly and the second nuclear fuel assembly in the refueling machine of the nuclear power plant based on the third load data.

[0027] Optionally, the third load data includes the height coordinates of the lifting mechanism corresponding to the overload / underload fault warning.

[0028] Specifically, the second determination unit is configured to:

[0029] Obtain the standard height of the lifting mechanism at which the grid bars of the first overload / underload grid layer in the first nuclear fuel assembly are hooked to the grid bars of the second overload / underload grid layer in the second nuclear fuel assembly.

[0030] Determine the hooking state of the grid bars of the nuclear fuel assemblies in the refueling machine of the nuclear power plant based on the height coordinates of the lifting mechanism and the standard height of the lifting mechanism.

[0031] Optionally, the second determination unit is specifically configured to:

[0032] Obtain the first standard grid height of the first overload / underload grid layer in the first nuclear fuel assembly, the second standard grid height of the second overload / underload grid layer in the second nuclear fuel assembly, the standard grid length, and the standard coordinates of the lower nozzle.

[0033] Determine the standard height of the lifting mechanism at which the grid bars of the first nuclear fuel assembly are hooked to the grid bars of the second nuclear fuel assembly based on the first standard grid height, the second standard grid height, the standard grid length, and the standard coordinates of the lower nozzle.

[0034] According to one aspect of the present disclosure, an electronic device is provided, including a memory and a processor. The memory stores a computer program, and when the processor executes the computer program, the data processing method of the refueling machine of the nuclear power plant as described above is implemented.

[0035] According to one aspect of the present disclosure, a computer-readable storage medium is provided. The storage medium stores a computer program, and when the computer program is executed by a processor, the data processing method of the refueling machine of the nuclear power plant as described above is implemented.

[0036] In the embodiments of the present disclosure, first, the initial first load data of the target load operation is obtained, then the second load data during the execution of the target load operation is obtained according to the data acquisition period, and finally the historical load data of the historical load operation corresponding to the target load operation is obtained. The load data is collected by the controller in the nuclear power plant refueling machine from multiple data dimensions corresponding to the nuclear power plant refueling machine. Therefore, the load data collected in the embodiments of the present disclosure includes data in multiple dimensions during the load operation. Compared with the data in a single dimension, the comprehensiveness of data acquisition is greatly improved. When performing mechanical analysis on the target load operation based on the initial first load data, the periodic second load data, and the historical load data, both the real-time change of the load data during the execution of the target load operation can be considered, and the historical load data can be used as an evaluation reference. In this way, the comprehensiveness is improved from both aspects of data acquisition and data analysis, thereby improving the accuracy of safety analysis.

[0037] Other features and advantages of the present disclosure will be described in the following specification, and part of them will become obvious from the specification, or be understood by implementing the present disclosure. The objectives and other advantages of the present disclosure can be achieved and obtained through the structures specifically pointed out in the specification, the claims, and the drawings. Brief Description of the Drawings

[0038] The drawings are used to provide a further understanding of the technical solutions of the present disclosure, and constitute a part of the specification. They are used to explain the technical solutions of the present disclosure together with the embodiments of the present disclosure, and do not constitute a limitation to the technical solutions of the present disclosure.

[0039] Figure 1 is the system architecture diagram of the application of the nuclear power plant refueling machine data processing method according to the embodiments of the present disclosure;

[0040] Figure 2 is the flowchart of the nuclear power plant refueling machine data processing method provided by an embodiment of the present disclosure;

[0041] Figure 3 is a schematic diagram of data communication between a computer device and a nuclear power plant refueling machine according to an embodiment of the present disclosure;

[0042] Figure 4 is a schematic diagram of data communication between the nuclear power plant refueling machine data processing application program, the database, and the programmable logic controller according to an embodiment of the present disclosure;

[0043] Figure 5 is an interface schematic diagram of displaying the load trend data of different data dimensions on a visualization interface according to an embodiment of the present disclosure;

[0044] Figure 6AIt is a schematic diagram of an interface for displaying over - underload warnings during under - load conditions on a visualization interface according to an embodiment of the present disclosure;

[0045] Figure 6B It is a schematic diagram of an interface for displaying over - underload warnings during over - load conditions on a visualization interface according to an embodiment of the present disclosure;

[0046] Figure 7 It is a schematic diagram of the height of each layer of grid in a fuel assembly according to an embodiment of the present disclosure;

[0047] Figure 8A It is a schematic diagram of the grid bars of the first nuclear fuel assembly being hooked to those of the second nuclear fuel assembly during over - load conditions according to an embodiment of the present disclosure;

[0048] Figure 8B It is a schematic diagram of the grid bars of the first nuclear fuel assembly being hooked to those of the second nuclear fuel assembly during under - load conditions according to an embodiment of the present disclosure;

[0049] Figure 9 It is a flowchart for responding to over - underload fault warnings and determining whether the grid bars in the nuclear fuel assembly are hooked according to an embodiment of the present disclosure;

[0050] Figure 10 It is a structural block diagram of a data processing device for a nuclear power plant refueling machine according to an embodiment of the present disclosure;

[0051] Figure 11 It is a structural diagram of a terminal for implementing the various methods according to an embodiment of the present disclosure;

[0052] Figure 12 It is a structural diagram of a server for implementing the various methods according to an embodiment of the present disclosure. Detailed implementation manners

[0053] In order to make the objectives, technical solutions and advantages of the present disclosure more clear and understandable, the present disclosure will be further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain the present disclosure and are not used to limit the present disclosure.

[0054] Before further elaborating on the embodiments of the present disclosure, the nouns and terms involved in the embodiments of the present disclosure are explained. The nouns and terms involved in the embodiments of the present disclosure are applicable to the following explanations:

[0055] Nuclear power plant refueling machine: It is a transfer equipment for nuclear reactor fuel assemblies and is a key device in the nuclear fuel transportation and storage system. It is responsible for completing the tasks of removing spent fuel from the reactor and loading new fuel into the reactor. Through the coordinated actions of the gripper and the guiding and pressing tube on the refueling machine, the transportation of nuclear fuel assemblies between the reactor and the transfer system is achieved.

[0056] Nuclear fuel assembly: The nuclear fuel assembly is the core part in a nuclear reactor, responsible for generating nuclear reactions to produce energy.

[0057] Grid: The grid is a key component in the nuclear fuel assembly, responsible for supporting and fixing the fuel rods to ensure their stability and safety in the reactor.

[0058] Lifting mechanism: A key component responsible for taking out or loading the fuel assembly from / to the reactor.

[0059] In the related art, when collecting load data in a nuclear fuel refueling machine, usually only an external recorder can be used to collect a single piece of data in the nuclear fuel refueling machine. For example, a single weight data or a single lifting height data, etc. Moreover, using an external recorder for data collection can only view the currently collected data value and cannot record the data value. In this way, the data dimension of the collected load data is relatively single, and the accuracy of load operation safety analysis based on this is also relatively low. To solve this technical problem, the present disclosure provides a data processing method for a nuclear power plant refueling machine, in order to improve the accuracy of load operation safety analysis.

[0060] System architecture applied in the embodiments of the present disclosure

[0061] Figure 1 It is a system architecture diagram applied to the data processing method for a nuclear power plant refueling machine according to the embodiments of the present disclosure. It includes a terminal 140, the Internet 130, a gateway 120, a server 110, etc.

[0062] The terminal 140 includes various forms such as a desktop computer, a laptop computer, a PDA (Personal Digital Assistant), a mobile phone, a vehicle-mounted terminal, a home theater terminal, a dedicated terminal, etc. In addition, it can be a single device or a set composed of multiple devices. For example, multiple devices are connected through a local area network and share a display device for collaborative work, jointly constituting a terminal 140. The terminal 140 can also communicate with the Internet 130 in a wired or wireless manner to exchange data.

[0063] The server 110 refers to a computer system that can provide certain services to the terminal 140. Compared with an ordinary terminal 140, the server 110 has high requirements in terms of stability, security, performance, etc. The server 110 can be a high-performance computer in a network platform, a cluster of multiple high-performance computers, a part (such as a virtual machine) allocated from a high-performance computer, a combination of parts (such as virtual machines) allocated from multiple high-performance computers, etc.

[0064] The gateway 120 is also known as an internetwork connector or protocol converter. The gateway realizes network interconnection at the transport layer and is a computer system or device that acts as a converter. Between two systems using different communication protocols, data formats, or languages, and even with completely different architectures, the gateway is a translator. At the same time, the gateway can also provide filtering and security functions. Messages sent from the terminal 140 to the server 110 need to be sent to the corresponding server 110 through the gateway 120. Messages sent from the server 110 to the terminal 140 also need to be sent to the corresponding terminal 140 through the gateway 120.

[0065] The method for processing data of the refueling machine of a nuclear power plant according to an embodiment of the present disclosure can be fully implemented in the terminal 140; can be fully implemented in the server 110; or can be partially implemented in the terminal 140 and partially implemented in the server 110.

[0066] General description of embodiments of the present disclosure

[0067] According to an embodiment of the present disclosure, a method for processing data of a refueling machine of a nuclear power plant is provided. This method can be integrated into an application program for processing data of a refueling machine of a nuclear power plant and applied to a device for processing data of a nuclear fuel refueling machine. This device for processing data of a nuclear fuel refueling machine can be integrated in a computer device, and the computer device can specifically be the terminal 140 or the server 110.

[0068] In one implementation, as Figure 2 shown, the method for processing data of a refueling machine of a nuclear power plant provided by the embodiment of the present disclosure includes:

[0069] Step 210, in response to a target load operation in the refueling machine of a nuclear power plant, obtain first load data corresponding to the target load operation in the refueling machine of a nuclear power plant;

[0070] Step 220, determine a data acquisition period, and obtain second load data during the execution of the target load operation in the refueling machine of a nuclear power plant based on the data acquisition period;

[0071] Step 230, obtain historical load data of historical load operations corresponding to the target load operation;

[0072] Step 240, perform a mechanical analysis on the target load operation based on the first load data, the second load data, and the historical load data.

[0073] In step 210, in response to a target load operation in the refueling machine of a nuclear power plant, first load data corresponding to the target load operation in the refueling machine of a nuclear power plant can be obtained.

[0074] The target payload operation in a nuclear power plant refueling machine may include the process of removing spent fuel assemblies from the reactor and loading new fuel assemblies into the reactor. Spent fuel assemblies and new fuel assemblies are two different types of nuclear fuel assemblies in a nuclear reactor. A spent fuel assembly is the nuclear fuel unloaded from the reactor after reacting to a certain extent. A new fuel assembly refers to the storage before the nuclear fuel is loaded into the reactor, which can be directly loaded into the nuclear reactor to provide energy for the nuclear reaction.

[0075] When the target payload operation starts to be executed in the nuclear fuel refueling machine, the first payload data corresponding to the target payload operation in the nuclear power plant refueling machine can be obtained. The first payload data is collected by the controller in the nuclear power plant refueling machine from multiple data dimensions of the nuclear power plant refueling machine.

[0076] The controller can be the part in the nuclear power plant refueling machine that is used to collect data and control the operation of the refueling machine. In one implementation, the controller in the nuclear power plant refueling machine can be a Programmable Logic Controller (PLC). The PLC is an important part of the control system of the nuclear power plant refueling machine, responsible for realizing data collection, logic control, etc. of the refueling machine. The PLC can collect data from multiple data dimensions of the nuclear power plant refueling machine. During the operation of the nuclear power plant refueling machine, the PLC can periodically scan the nuclear power plant refueling machine. To meet the real-time requirement of data collection, the scan cycle can be less than 10 ms.

[0077] The multiple data dimensions for collecting the first payload data can include the operation step number of the target payload operation, the height coordinate of the lifting mechanism, and the load weight, etc.

[0078] The operation step number can be the operation step number of the target payload operation. Since the nuclear power plant refueling machine needs to strictly follow the pre-set operation steps step by step during the process of loading and unloading nuclear fuel, the accurate execution of each step plays a crucial role in the safety of the loading and unloading process. Therefore, the operation step number can be used to clarify the operation sequence of different operation steps and to count the payload data of each step.

[0079] The height coordinate of the lifting mechanism can be the height coordinate of the lifting mechanism when loading and unloading nuclear fuel assemblies during the execution of the target payload operation. Obtaining the height coordinate of the lifting mechanism can ensure that the nuclear fuel assembly is accurately and safely moved to the designated position during the refueling process, and through precise height control, the risk during the operation process can be reduced and damage to the nuclear reactor can be avoided.

[0080] The load weight can be the weight data of the load carried by the lifting mechanism during the execution of the target payload operation. Obtaining the lifting weight data can reduce the risk during the operation process through precise load control.

[0081] In one embodiment, the process of data collection by the PLC in the nuclear power plant refueling machine and transmitting the collected data to the computer device for implementing the data processing method of the nuclear power plant refueling machine according to the embodiments of the present disclosure can be represented as Figure 3 . In Figure 3 , a programmable logic controller (PLC) can collect data in the nuclear power plant refueling machine, connect to an Ethernet switch through an Ethernet cable, and transmit the collected data to the computer device through the Ethernet switch. In addition, the nuclear power plant refueling machine may further include a supervisor programmable logic controller (SPLC) and a human-machine interaction (HMI). The SPLC can be used to detect and control the entire nuclear power plant refueling machine system and can also be used for data collection. Therefore, the SPLC can collect data simultaneously with the PLC. When the PLC misses data during the data collection process, the SPLC can supplement the collection to further ensure the comprehensiveness of data collection. The HMI can be used to provide an intuitive operation interface for the nuclear power plant refueling machine, facilitating the operator to control the nuclear fuel loading and unloading process. During the data collection process, some data dimensions may need to be conveyed through the operator's operation instructions. Therefore, the HMI can also be used to transmit data to the computer device. The SPLC and the HMI can also be connected to the Ethernet switch through an Ethernet cable and transmit the collected data to the computer device through the Ethernet switch.

[0082] In step 220, a data collection period can be determined, and second load data during the execution of the target load operation in the nuclear power plant refueling machine can be obtained based on the data collection period.

[0083] The data collection period can be the period for collecting data for the target load operation. For example, it can be 20 ms. The data collection period can be determined based on the real-time requirement for data collection. When the data collection period is greater than 20 ms and less than 30 ms, real-time data collection can be achieved.

[0084] Based on the data collection period, second load data during the execution of the target load operation in the nuclear power plant refueling machine is obtained. For example, if the data collection period is 20 ms, then the load data can be collected every 20 ms. The second load data can have the same data dimensions as the first load data and adopt the same data collection method as the first load data, that is, it is collected by the controller in the nuclear power plant refueling machine from multiple data dimensions, which will not be elaborated here.

[0085] After collecting the first load data and the second load data, the first load data and the second load data can be stored in the load information database. The load information database can be used to store the load data collected from the nuclear power plant refueling machine so that the load data can be called at any time for safety analysis.

[0086] In one implementation, after determining the data collection period and obtaining the second load data during the execution of the target load operation in the nuclear power plant refueling machine based on the data collection period, the data processing method for the nuclear power plant refueling machine further includes:

[0087] Determine the data recording period;

[0088] Based on the data recording period, store the first load data and the second load data in the load information database.

[0089] Since the second load data is collected according to the data collection period, if it is directly stored in the load information database every time the second load data is collected, the load information database may experience performance degradation due to too frequent data access and storage. Based on this, the first load data and the second load data can be stored according to the data recording period.

[0090] The data recording period can be the period for storing load data. For example, 100 ms, that is, load data is stored in the load information database every 100 ms. The data recording period can be determined based on the database storage performance and the data transmission performance.

[0091] After the first load data and the second load data are collected, the first load data and the second load data can be temporarily stored in the load information temporary database. Based on the data recording period, extract the first load data and the second load data stored in the load information temporary database within one data recording period and store them in the load information database.

[0092] Storing the first load data and the second load data in the load information database according to the data recording period realizes the batch storage of load data, so as to keep the storage performance of the database in the best state, which is beneficial to improving the data storage efficiency.

[0093] In step 230, the historical load data of the historical load operation corresponding to the target load operation can be obtained.

[0094] The historical load operation corresponding to the target load operation can be the load operation executed in the nuclear power plant refueling machine within a predetermined time period before the target load operation. The predetermined time period can be one day, one week, one month, etc. For example, the load operation within 30 days before the execution of the target load operation can be obtained as the target load operation.

[0095] Historical load data can be data collected during the execution of historical load operations, which may include initial data collected when the historical load operation occurred, as well as periodic data collected periodically during the execution process. The historical load data can have the same data dimension as the first load data and the second load data. The historical load data can be obtained from the load information database.

[0096] As can be seen from steps 210 to 230, the method for processing nuclear power plant refueling machine data according to the embodiments of the present disclosure includes: the process of obtaining data from the nuclear power plant refueling machine by the nuclear power plant refueling machine data processing application, the process of storing the collected data in the load information database, and the process of obtaining historical load data from the load information database. The above processes can be described as a data interaction process among a nuclear power plant refueling machine, a load information database, and a nuclear power plant refueling machine data processing application program. In one embodiment, when the controller is a programmable logic controller, the data interaction process can be specifically represented as Figure 4 .

[0097] In Figure 4 , after collecting the load data, the programmable logic controller (PLC) can transmit the load data through the input / output device and store the data in the load information temporary database through the data communication interface. The data communication interface can be a DAServer interface (DASABCIP), which is a communication interface for connecting a data acquisition system and an industrial control system. In the embodiments of the present disclosure, it can be used for data interaction and communication between the load information temporary database and the PLC. The communication protocol can adopt a dynamic data exchange mechanism (DDE) or SuiteLink. Both of these protocols can achieve data exchange and communication between application programs, and at the same time, real-time data transfer between the PLC and the load information temporary database can be supported by creating an access name for the input / output device.

[0098] The load information temporary database can be a WindowViewer Runtime database, which is a database for storing and managing data in an industrial automation system. Its main function is to provide a unified data storage and access method to support various devices and application programs in the industrial system. The load information temporary database can interact with the load information database, specifically through a database access program programming interface, such as an ODBC interface, which is an application program programming interface for accessing databases. It allows application programs to communicate with various different databases in the same way without having to understand the specific details of the databases.

[0099] The data processing application of the nuclear power plant refueling machine can exchange data with the load information temporary storage database or the load information database. When exchanging data with the load information temporary storage database, it can obtain the first load data and the second load data corresponding to the target load operation collected by the PLC. When exchanging data with the load information database, it can obtain the historical load data. When the data processing application of the nuclear power plant refueling machine accesses the load information temporary storage database or the load information database, it can also perform operations such as modifying, creating, or deleting data tables in the database. When the data processing application of the nuclear power plant refueling machine interacts with the database, it can use the database access program programming interface, such as the ODBC interface. When accessing the load information temporary storage database and the load information database, the database access manager can manage the database access permissions to ensure data integrity and security.

[0100] In step 240, a mechanical analysis of the target load operation can be performed based on the first load data, the second load data, and the historical load data.

[0101] Performing a mechanical analysis of the target load operation can be used to determine safety by analyzing the stability and load-bearing capacity of the equipment in the nuclear power plant refueling machine. The load data can include the height coordinates of the lifting mechanism and the load weight. The height coordinates of the lifting mechanism determine the working range and potential danger areas of the nuclear power plant refueling machine, and the load weight affects the stability and load-bearing capacity of the nuclear power plant refueling machine. Therefore, by comprehensively analyzing the height of the lifting mechanism and the load weight, the safety of the nuclear power plant refueling machine during the execution of the target load operation can be evaluated.

[0102] In one implementation, performing a mechanical analysis of the target load operation based on the first load data, the second load data, and the historical load data includes:

[0103] Constructing load trend data based on the first load data, the second load data, and the historical load data;

[0104] Performing a mechanical analysis of the target load operation based on the load trend data.

[0105] The load trend data can represent the change of load data over time in chronological order. After constructing the load trend data, the load trend data can be visually displayed in the form of a trend chart on the visualization interface, so that the operator can visually perform a mechanical analysis of the target load operation based on the visualization trend chart and make an operation response in a timely manner according to the trend change.

[0106] In one implementation, constructing load trend data based on the first load data, the second load data, and the historical load data includes:

[0107] For multiple data dimensions, obtain the first sub-load data, second sub-load data, and historical sub-load data corresponding to each data dimension from the first load data, second load data, and historical load data;

[0108] Construct load trend data corresponding to each data dimension based on the first sub-load data, second sub-load data, and historical sub-load data corresponding to each data dimension.

[0109] Since the PLC can collect data of multiple data dimensions during data acquisition. Therefore, load trend data corresponding to each data dimension can be constructed. For example, the multiple data dimensions include the operation step number, the height coordinate of the lifting mechanism, and the load weight, and the load trend data corresponding to the operation step number, the load trend data corresponding to the height coordinate of the lifting mechanism, and the load trend data corresponding to the load weight can be constructed respectively.

[0110] The visualization trend charts corresponding to the load trend data of different data dimensions can be displayed in pages on the visualization interface, or can be displayed on the visualization interface after integration. For example Figure 5 As shown, multiple trend lines corresponding to the height coordinate of the lifting mechanism, the operation step number, and the load weight are displayed in the visualization interface. In the visualization interface, the load data at the corresponding position can also be displayed by dragging the time axis. For example, at time point T1, the height coordinate of the lifting mechanism is 3998.1, the operation step number is 1, and the load weight is 678.0.

[0111] Constructing load trend data for multiple data dimensions respectively is beneficial to intuitively obtain the data changes of each data dimension, and performing mechanical analysis through the data changes of different data dimensions is beneficial to further improve the accuracy of safety analysis.

[0112] By constructing load trend data, the change of load data during the execution of the target load operation can be obtained more intuitively, as well as the data comparison between the target load operation and the historical load operation. Therefore, performing mechanical analysis on the target load operation based on the load trend data is beneficial to improving the accuracy of mechanical analysis.

[0113] In the above embodiment, trend data is constructed to record and display the first load data, second load data, and historical load data. In another embodiment, mechanical analysis of the target load operation is performed based on the first load data, second load data, and historical load data, including: constructing a load data table based on the first load data, second load data, and historical load data; performing mechanical analysis on the target load operation based on the load data table.

[0114] The load data table can display each load data in chronological order. As shown in Table 1 for example:

[0115]

[0116]

[0117] Table 1

[0118] In Table 1, a load data table for recording first load data, second load data, and historical load data is shown, including load data identification, operation step number, lifting mechanism height coordinate, load weight, and acquisition time.

[0119] Performing a mechanical analysis based on the load data table can also intuitively obtain the changes in load data during the execution of the target load operation, as well as the comparison of load data between the target load operation and the historical load operation, which is beneficial to improving the accuracy of the mechanical analysis.

[0120] Constructing load trend data and recording data in the load data table can be carried out simultaneously to achieve redundancy settings and prevent data loss when recording data in a single way.

[0121] The data processing method of the nuclear power plant refueling machine in the embodiments of the present disclosure can also be used to determine the hook state of the grid strips of the nuclear fuel assembly.

[0122] In one implementation, the data processing method of the nuclear power plant refueling machine further includes:

[0123] During the execution of the target load operation, when receiving an over / under load fault warning between the first nuclear fuel assembly and the second nuclear fuel assembly in the nuclear power plant refueling machine, obtain the third load data corresponding to the over / under load fault warning;

[0124] Based on the third load data, determine the hook state of the grid strips between the first nuclear fuel assembly and the second nuclear fuel assembly in the nuclear power plant refueling machine.

[0125] After the nuclear fuel assemblies are in place in the reactor, the designed theoretical gap between the nuclear fuel assemblies is about 1 millimeter. After the reaction occurs under superimposed irradiation, the nuclear fuel assemblies may be squeezed against each other, the friction force increases, and even the grid strips may be hooked. When the grid strips are hooked, the over / under load protection action of the nuclear power plant refueling machine will be triggered and the lifting movement will stop. When the over / under load is caused by the grid strip hooking, if the stress applied to the grid strip cannot be eliminated in time, it is very likely to cause plastic deformation or even fracture of the grid strip, and then the nuclear fuel assembly cannot meet the requirement of being reinserted into the reactor. If a timely response can be made to the over / under load fault and the stress on the grid strip can be eliminated, the reusability of the nuclear fuel assembly can be improved and economic losses can be avoided.

[0126] The over - under load fault warning can be collected and issued by the PLC when over - under load faults occur in the first nuclear fuel assembly and the second nuclear fuel assembly. The over - under load can be judged based on the load weight. For example, when the actual weight is greater than the standard weight plus 80, an overload warning is issued, and when the actual weight is less than the standard weight minus 80, an under - load warning is issued. The over - under load fault is divided into an overload condition and an under - load condition. The overload condition occurs when the nuclear fuel assembly is unloaded by the nuclear power plant refueling machine and the nuclear fuel assembly moves upward. The under - load condition occurs when the nuclear fuel assembly is loaded by the nuclear power plant refueling machine and the nuclear fuel assembly moves downward.

[0127] The third load data corresponding to the over - under load fault warning may include the operation step number, the height coordinate of the lifting mechanism, and the load weight.

[0128] After receiving the third load data corresponding to the over - under load fault warning, the third load data can be displayed in the visualization interface of the nuclear power plant refueling machine data processing application and highlighted, so that the operator can view the over - under load warning in time and make a response. For example Figure 6A and Figure 6B as shown. Figure 6A The third load data shown in the visualization interface in the under - load condition is shown, including: operation step number 65, height coordinate of the lifting mechanism 8817, and load weight 1187. Figure 6B The third load data shown in the visualization interface in the overload condition is shown, including: operation step number 46, height coordinate of the lifting mechanism 8391, and load weight 1386.

[0129] After obtaining the third load data, the third load data can also be recorded in the load information database. The load information data can include an over - under load data table, which records the load data corresponding to multiple over - under load fault warnings. The database information writing can use the data insertion instruction of the SQL language. Recording the third load data into the over - under load data table in the load information database can realize the ready access to the data related to the over - under load condition, provide data support for the subsequent analysis of the over - under load condition, and thus improve the accuracy of the over - under load condition analysis.

[0130] The over - under load data table can be as shown in Table 2:

[0131] Operation step number Nuclear fuel assembly number Over / under load type Lifting mechanism height coordinate Load weight 6 YQX097 Under load 6560 1310 15 YQX05K Under load 8817 1310 15 YQX08B Overload 7869 1310 62 YQX08B Under load 4500 1270 62 YQX08B Overload 8817 1187 …… …… …… …… ……

[0132] Table 2

[0133] In Table 2, it shows that the third load data includes the operation step number, the nuclear fuel assembly number, the over - under load type, the height coordinate of the lifting mechanism, and the load weight.

[0134] After obtaining the third load data, the grid bar hooking state of the first nuclear fuel assembly and the second nuclear fuel assembly in the nuclear power plant refueling machine can be determined based on the third load data. The nuclear fuel hooking state can include hooked and unhooked.

[0135] In one implementation, the third load data includes the lifting mechanism height coordinates corresponding to the overload / underload fault warning; based on this, determining the grid bar hooking state of the first nuclear fuel assembly and the second nuclear fuel assembly in the nuclear power plant refueling machine based on the third load data includes:

[0136] Obtain the standard height of the lifting mechanism when the grid bars of the first overload / underload grid layer in the first nuclear fuel assembly are hooked to the grid bars of the second overload / underload grid layer in the second nuclear fuel assembly.

[0137] Determine the grid bar hooking state of the nuclear fuel assembly in the nuclear power plant refueling machine based on the lifting mechanism height coordinates and the standard height of the lifting mechanism.

[0138] The first overload / underload grid layer and the second overload / underload grid layer are respectively the grid layers that interfere in the first nuclear fuel assembly and the second nuclear fuel assembly when the overload / underload fault warning occurs. The standard height of the lifting mechanism can refer to the standard height value of the lifting mechanism when the grid bars of the first nuclear fuel assembly and the second nuclear fuel assembly are hooked.

[0139] In one implementation, obtaining the standard height of the lifting mechanism when the grid bars of the first overload / underload grid layer in the first nuclear fuel assembly are hooked to the grid bars of the second overload / underload grid layer in the second nuclear fuel assembly includes:

[0140] Obtain the first standard grid height of the first overload / underload grid layer in the first nuclear fuel assembly, the second standard grid height of the second overload / underload grid layer in the second nuclear fuel assembly, the standard grid length, and the standard coordinates of the lower nozzle.

[0141] Determine the standard height of the lifting mechanism when the grid bars of the first nuclear fuel assembly and the second nuclear fuel assembly are hooked based on the first standard grid height, the second standard grid height, the standard grid length, and the standard coordinates of the lower nozzle.

[0142] The first standard grid height can be the theoretical height value of the first overload / underload grid layer in the first nuclear fuel assembly in the in-core position state. Similarly, the second standard grid height can be the theoretical height value of the second overload / underload grid layer in the second nuclear fuel assembly in the in-core position state. For example Figure 7As shown in the schematic diagram of each layer of grid in the nuclear fuel assembly, the lower nozzle is the base of the nuclear fuel assembly, the upper nozzle is the top cover of the nuclear fuel assembly. The total height of the nuclear fuel assembly is 4062.7, and there are 8 layers of grids in total. The height of the first layer of grid is 140.45, the height of the second layer of grid is 760.9, and so on. The height of the eighth layer of grid is 3893.8. If the first over / under-loaded grid layer in the first nuclear fuel assembly is the fifth layer of grid, then the first standard grid height is 2326.9.

[0143] The standard grid length can be the length of each grid. For example, the standard grid length is 40. The standard coordinate of the lower nozzle can be the encoder elevation of the lower nozzle in the nuclear fuel assembly when it is in place in the reactor core. The encoder can be used to indicate the height coordinate value.

[0144] After determining the first standard grid height, the second standard grid height, the standard grid length, and the standard coordinate of the lower nozzle, the standard height of the lifting mechanism for the grid strip hook-up between the first nuclear fuel assembly and the second nuclear fuel assembly can be determined based on the first standard grid height, the second standard grid height, the standard grid length, and the standard coordinate of the lower nozzle.

[0145] For the overloaded condition and the under-loaded condition, the standard height of the lifting mechanism for the grid strip hook-up between the first nuclear fuel assembly and the second nuclear fuel assembly can be different.

[0146] In the overloaded condition, the grid strip hook-up between the first over / under-loaded grid layer in the first nuclear fuel assembly and the second over / under-loaded grid layer in the second nuclear fuel assembly can be expressed as Figure 8A . When there is a hook-up between the first over / under-loaded grid layer x in the first nuclear fuel assembly and the second over / under-loaded grid layer y in the second nuclear fuel assembly, the first standard grid height is H AX , the second standard grid height is H BY , the standard grid length is H GRID , and the standard coordinate of the lower nozzle can be expressed as H SD , which is not shown in the figure. Thus, in the overloaded condition, the standard height of the lifting mechanism can be expressed as Formula 1:

[0147] H AX,BY = H SD + H AX - H BY + H GRID (Formula 1).

[0148] In the under-loaded condition, the grid strip hook-up between the first over / under-loaded grid layer in the first nuclear fuel assembly and the second over / under-loaded grid layer in the second nuclear fuel assembly can be expressed as Figure 8BWhen hooking occurs between the first over-underloading grid layer x in the first nuclear fuel assembly and the second over-underloading grid layer y in the second nuclear fuel assembly, the first standard grid height is H AX , the second standard grid height is H BY , the standard grid length is H GRID , the standard coordinate of the lower nozzle can be expressed as H SD , which is not shown in the figure. Thus, in the underloading condition, the standard height of the lifting mechanism can be expressed by Formula 2:

[0149] H AX,BY = H SD + H AX - H BY - H GRID (Formula 2).

[0150] Calculating the standard height of the lifting mechanism based on the first standard grid height, the second standard grid height, the standard grid length, and the standard coordinate of the lower nozzle can be performed according to the actual parameters of the nuclear fuel assembly, avoiding inaccurate calculation of the standard height of the lifting mechanism caused by data deviation between different nuclear fuel assemblies, which is beneficial to improving the accuracy of calculating the standard height of the lifting mechanism.

[0151] After calculating the standard height of the lifting mechanism, the grid strip hooking state of the nuclear fuel assembly in the nuclear power plant refueling machine can be determined based on the height coordinate of the lifting mechanism and the standard height of the lifting mechanism. Specifically, determining the grid strip hooking state of the nuclear fuel assembly in the nuclear power plant refueling machine based on the height coordinate of the lifting mechanism and the standard height of the lifting mechanism includes: when the difference between the height coordinate of the lifting mechanism and the standard height of the lifting mechanism is less than or equal to a predetermined value, it is determined that the grid strip of the nuclear fuel assembly in the nuclear power plant refueling machine is hooked; otherwise, it is determined that the grid strip of the nuclear fuel assembly in the nuclear power plant refueling machine is not hooked.

[0152] Comparing the actual height of the lifting mechanism with the standard height of the lifting mechanism when the grid strip is hooked, and determining the grid strip hooking state of the nuclear fuel assembly through a reference value is beneficial to improving the accuracy of determining the grid strip hooking state.

[0153] In summary, the process of determining the grid strip hooking state can be expressed as Figure 9 . First, receive the over-underloading fault warning and read the height coordinate of the lifting mechanism; judge whether the grid strip is hooked based on the standard height of the lifting mechanism; for the convenience of operators to view and handle the fault, dynamically display the nuclear fuel assembly and the warning information on the visualization interface, and record the information in the database. Thus, when determining the grid strip hooking state, it is possible to respond promptly to the over-underloading fault warning, facilitate the operators to handle it in a timely manner, which is beneficial to improving the real-time performance of data processing, and further improving the safety of the operation process of the nuclear power plant refueling machine.

[0154] The load data collected in the embodiments of the present disclosure includes data in multiple dimensions during load operations. Compared with data in a single dimension, the comprehensiveness of data collection is greatly improved. When performing mechanical analysis on a target load operation based on initial first load data, periodic second load data, and historical load data, both the real-time change of load data during the execution of the target load operation can be considered, and historical load data can be used as an evaluation reference. In this way, the comprehensiveness is improved from both aspects of data collection and data analysis, thereby improving the accuracy of safety analysis. In addition, a more reasonable nuclear fuel loading plan can be analyzed and formulated based on the load data corresponding to the target load operation and historical load operations, reducing the probability of damage to nuclear fuel assemblies.

[0155] Description of the devices and equipment in the embodiments of the present disclosure

[0156] It can be understood that although the steps in the above-mentioned various flowcharts are sequentially shown according to the arrows, these steps are not necessarily executed in the order indicated by the arrows. Unless there is a clear description in this embodiment, the execution of these steps has no strict order limit, and these steps can be executed in other orders. Moreover, at least a part of the steps in the above-mentioned flowcharts may include multiple steps or multiple stages. These steps or stages are not necessarily executed at the same time, but can be executed at different times. The execution order of these steps or stages is not necessarily sequential, but can be executed alternately or in turn with at least a part of other steps or steps or stages in other steps.

[0157] It should be noted that in each specific embodiment of the present application, when it comes to performing relevant processing based on data related to the characteristics of the target object, such as target object attribute information or a set of attribute information, the permission or consent of the target object will be obtained first. Moreover, the collection, use, and processing of these data will comply with the relevant laws, regulations, and standards of relevant countries and regions. In addition, when the embodiments of the present application need to obtain target object attribute information, the separate permission or separate consent of the target object will be obtained by means of a pop-up window or jumping to a confirmation page. After clearly obtaining the separate permission or separate consent of the target object, the necessary target object-related data for the normal operation of the embodiments of the present application will be obtained.

[0158] Figure 10 It is a structural diagram of the nuclear power plant refueling machine data processing device 1000 provided by the embodiments of the present disclosure.

[0159] The device includes:

[0160] The first acquisition unit 1010 is configured to acquire first load data corresponding to a target load operation in a nuclear power plant refueling machine in response to the target load operation in the nuclear power plant refueling machine, where the first load data is collected by a controller in the nuclear power plant refueling machine from multiple data dimensions of the nuclear power plant refueling machine;

[0161] The second acquisition unit 1020 is configured to determine a data acquisition period and acquire second load data during the execution of the target load operation in the nuclear power plant refueling machine based on the data acquisition period;

[0162] The third acquisition unit 1030 is configured to acquire historical load data of a historical load operation corresponding to the target load operation;

[0163] The mechanical analysis unit 1040 is configured to perform a mechanical analysis on the target load operation based on the first load data, the second load data, and the historical load data.

[0164] Optionally, the mechanical analysis unit 1040 is specifically configured to:

[0165] Construct load trend data based on the first load data, the second load data, and the historical load data;

[0166] Perform a mechanical analysis on the target load operation based on the load trend data.

[0167] Optionally, the mechanical analysis unit 1040 is specifically configured to:

[0168] For multiple data dimensions, acquire first sub-load data, second sub-load data, and historical sub-load data corresponding to each data dimension from the first load data, the second load data, and the historical load data;

[0169] Construct load trend data corresponding to each data dimension based on the first sub-load data, the second sub-load data, and the historical sub-load data corresponding to each data dimension.

[0170] Optionally, the nuclear power plant refueling machine data processing device 1000 further includes:

[0171] The first determination unit (not shown) is configured to determine a data recording period;

[0172] The storage unit (not shown) is configured to store the first load data and the second load data in a load information database based on the data recording period.

[0173] Optionally, the nuclear power plant refueling machine data processing device 1000 further includes:

[0174] A fourth acquisition unit (not shown), configured to acquire third load data corresponding to the over / under load fault warning when receiving the over / under load fault warning between the first nuclear fuel assembly and the second nuclear fuel assembly in the nuclear power plant refueling machine during the execution of the target payload operation;

[0175] A second determination unit (not shown), configured to determine the grid strip hooking state between the first nuclear fuel assembly and the second nuclear fuel assembly in the nuclear power plant refueling machine based on the third load data.

[0176] Optionally, the third load data includes the hoisting mechanism height coordinates corresponding to the over / under load fault warning;

[0177] The second determination unit (not shown) is specifically configured to:

[0178] Acquire the standard height of the hoisting mechanism when the first over / under load grid layer in the first nuclear fuel assembly and the second over / under load grid layer in the second nuclear fuel assembly have grid strip hooking;

[0179] Determine the grid strip hooking state of the nuclear fuel assembly in the nuclear power plant refueling machine based on the hoisting mechanism height coordinates and the standard height of the hoisting mechanism.

[0180] Optionally, the second determination unit (not shown) is specifically configured to:

[0181] Acquire the first standard grid height of the first over / under load grid layer in the first nuclear fuel assembly, the second standard grid height of the second over / under load grid layer in the second nuclear fuel assembly, the standard grid length, and the standard coordinates of the lower tube seat;

[0182] Determine the standard height of the hoisting mechanism when the first nuclear fuel assembly and the second nuclear fuel assembly have grid strip hooking based on the first standard grid height, the second standard grid height, the standard grid length, and the standard coordinates of the lower tube seat.

[0183] Refer to Figure 11 , Figure 11 is a structural block diagram of a part of the target terminal 140 for implementing the embodiments of the present disclosure. The target terminal 140 includes components such as a radio frequency (RF) circuit 1110, a memory 1115, an input unit 1130, a display unit 1140, a sensor 1150, an audio circuit 1160, a wireless fidelity (WiFi) module 1170, a processor 1180, and a power supply 1190. Those skilled in the art can understand that Figure 11 the shown structure of the target terminal 140 does not limit the mobile phone or computer, and may include more or fewer components than shown, or combine certain components, or have different component arrangements.

[0184] The RF circuit 1110 can be used for receiving and transmitting information or signals during communication. Specifically, after receiving the downlink information from the base station, it is processed by the processor 1180. Additionally, the uplink data is sent to the base station.

[0185] The memory 1115 can be used to store software programs and modules. The processor 1180 executes various functional applications and data processing of the target terminal 140 by running the software programs and modules stored in the memory 1115.

[0186] The input unit 1130 can be used to receive input digital or character information, and generate key signal inputs related to the settings and function controls of the target terminal 140. Specifically, the input unit 1130 can include a touch panel 1131 and other input devices 1132.

[0187] The display unit 1140 can be used to display input information or provided information, as well as various menus of the target terminal 140. The display unit 1140 can include a display panel 1141.

[0188] The audio circuit 1160, speaker 1161, and microphone 1162 can provide an audio interface.

[0189] In this embodiment, the processor 1180 included in the target terminal 140 can execute the data processing method of the nuclear power plant refueling machine in the previous embodiment.

[0190] The target terminal 140 in the embodiments of the present disclosure includes, but is not limited to, mobile phones, computers, intelligent voice interaction devices, etc. The embodiments of the present invention can be applied to various scenarios, including but not limited to nuclear fission experiments, nuclear power generation, etc.

[0191] Figure 12 It is a structural block diagram of a part of the server 110 for implementing the embodiments of the present disclosure. The server 110 can vary significantly due to different configurations or performances, and can include one or more central processing units (CPUs) 1222 (for example, one or more processors) and a memory 1232, and one or more storage media 1230 (for example, one or more mass storage devices) for storing application programs 1242 or data 1244. Among them, the memory 1232 and the storage media 1230 can be transient storage or persistent storage. The programs stored in the storage media 1230 can include one or more modules (not shown in the figure), and each module can include a series of instruction operations for the server 110. Further, the central processor 1222 can be configured to communicate with the storage media 1230 and execute a series of instruction operations in the storage media 1230 on the server 110.

[0192] The server 110 may further include one or more power supplies 1226, one or more wired or wireless network interfaces 1250, one or more input / output interfaces 1258, and / or one or more operating systems 1241, such as Windows ServerTM, Mac OS XTM, UnixTM, LinuxTM, FreeBSDTM, and so on.

[0193] The central processing unit 1222 in the server 110 may be used to execute the nuclear power plant refueling machine data processing method of the embodiments of the present disclosure.

[0194] The embodiments of the present disclosure further provide a computer-readable storage medium, which is used to store program codes, and the program codes are used to execute the nuclear power plant refueling machine data processing methods of the foregoing various embodiments.

[0195] The embodiments of the present disclosure further provide a computer program product, which includes a computer program. The processor of the computer device reads and executes the computer program, so that the computer device executes to implement the above-mentioned nuclear power plant refueling machine data processing method.

[0196] Terms such as "first", "second", "third", "fourth", etc. (if any) in the specification of the present disclosure and the above-mentioned drawings are used to distinguish similar objects, and do not necessarily have to be used to describe a specific order or sequence. It should be understood that the data used in this way can be interchanged under appropriate circumstances, so that the embodiments of the present disclosure described herein can be implemented in an order other than those illustrated or described herein. In addition, the terms "include" and "comprise" and any variations thereof are intended to cover non-exclusive inclusion. For example, a process, method, system, product, or device that includes a series of steps or units does not necessarily have to be limited to those steps or units clearly listed, but may include other steps or units that are not clearly listed or are inherent to these processes, methods, products, or devices.

[0197] It should be understood that in this disclosure, "at least one (item)" means one or more, and "a plurality" means two or more. "And / or" is used to describe the association relationship of associated objects, indicating that there can be three relationships. For example, "A and / or B" can mean: only A exists, only B exists, and both A and B exist at the same time. Among them, A and B can be singular or plural. The character " / " generally indicates that the associated objects before and after are in an "or" relationship. "At least one (one) of the following" or its similar expressions refer to any combination of these items, including any combination of single items (ones) or plural items (ones). For example, at least one (one) of a, b, or c can mean: a, b, c, "a and b", "a and c", "b and c", or "a and b and c", where a, b, c can be single or multiple.

[0198] It should be understood that in the description of the embodiments of this disclosure, the meaning of "a plurality (or multiple items)" is more than two. Understandings such as greater than, less than, exceeding, etc. do not include the present number, and understandings such as above, below, within, etc. include the present number.

[0199] In several embodiments provided in this disclosure, it should be understood that the disclosed systems, devices, and methods can be implemented in other ways. For example, the device embodiments described above are merely illustrative. For example, the division of units is only a logical function division. In actual implementation, there can be other division methods. For example, multiple units or components can be combined or integrated into another system, or some features can be ignored or not executed. Another point is that the displayed or discussed couplings or direct couplings or communication connections to each other can be through some interfaces, and the indirect couplings or communication connections of devices or units can be in electrical, mechanical, or other forms.

[0200] The units described as separate components may or may not be physically separated, and the components displayed as units may or may not be physical units, that is, they can be located in one place, or distributed to multiple network units. Some or all of the units can be selected according to actual needs to achieve the purpose of the solution of this embodiment.

[0201] In addition, the functional units in each embodiment of this disclosure can be integrated into one processing unit, or each unit can exist physically alone, or two or more units can be integrated into one unit. The above-mentioned integrated units can be implemented in the form of hardware or in the form of software functional units.

[0202] When the integrated unit is implemented in the form of a software functional unit and sold or used as an independent product, it can be stored in a computer-readable storage medium. Based on such an understanding, the technical solution of the present disclosure, in essence, or the part that contributes to the prior art, or all or part of the technical solution, can be embodied in the form of a software product. This computer software product is stored in a storage medium and includes several instructions for causing a computer device (which may be a personal computer, a server, or a network device, etc.) to execute all or part of the steps of the methods of the various embodiments of the present disclosure. The aforementioned storage medium includes: various media such as USB flash drives, mobile hard disks, read-only memories (ROM), random access memories (RAM), magnetic disks, or optical discs that can store program codes.

[0203] It should also be understood that the various embodiments provided by the present disclosure can be combined arbitrarily to achieve different technical effects.

[0204] The above is a specific description of the embodiments of the present disclosure, but the present disclosure is not limited to the above embodiments. Those skilled in the art can also make various equivalent deformations or substitutions without departing from the spirit of the present disclosure, and these equivalent deformations or substitutions are all included within the scope defined by the claims of the present disclosure.

Claims

1. A data processing method for a nuclear power plant refueling machine, characterized in that, Including: In response to a target load operation in a nuclear power plant refueling machine, obtaining first load data corresponding to the target load operation in the nuclear power plant refueling machine, where the first load data is collected by a controller in the nuclear power plant refueling machine from multiple data dimensions of the nuclear power plant refueling machine; Determining a data collection period, and obtaining second load data during the execution of the target load operation in the nuclear power plant refueling machine based on the data collection period; Obtaining historical load data of a historical load operation corresponding to the target load operation; Performing a mechanical analysis on the target load operation based on the first load data, the second load data, and the historical load data.

2. The method according to claim 1, wherein The performing a mechanical analysis on the target load operation based on the first load data, the second load data, and the historical load data includes: Constructing load trend data based on the first load data, the second load data, and the historical load data; Performing a mechanical analysis on the target load operation based on the load trend data.

3. The method according to claim 2, wherein The constructing load trend data based on the first load data, the second load data, and the historical load data includes: For multiple data dimensions, obtaining first sub-load data, second sub-load data, and historical sub-load data corresponding to each data dimension from the first load data, the second load data, and the historical load data; Constructing load trend data corresponding to each data dimension based on the first sub-load data, the second sub-load data, and the historical sub-load data corresponding to each data dimension.

4. The method according to claim 1, wherein After determining the data collection period and obtaining second load data during the execution of the target load operation in the nuclear power plant refueling machine based on the data collection period, the method further includes: Determining a data recording period; Storing the first load data and the second load data in a load information database based on the data recording period.

5. The method according to claim 1, wherein The method further includes: During the execution of the target load operation, when receiving an over-under load fault warning between a first nuclear fuel assembly and a second nuclear fuel assembly in the nuclear power plant refueling machine, obtaining third load data corresponding to the over-under load fault warning; Determining the grid strip hooking state between the first nuclear fuel assembly and the second nuclear fuel assembly in the nuclear power plant refueling machine based on the third load data.

6. The method according to claim 5, wherein The third load data includes the lifting mechanism height coordinates corresponding to the over-under load fault warning; The determining the grid strip hooking state between the first nuclear fuel assembly and the second nuclear fuel assembly in the nuclear power plant refueling machine based on the third load data includes: Obtaining the standard height of the lifting mechanism when grid strips are hooked between a first over-under load grid layer in the first nuclear fuel assembly and a second over-under load grid layer in the second nuclear fuel assembly; Determining the grid strip hooking state of the nuclear fuel assembly in the nuclear power plant refueling machine based on the lifting mechanism height coordinates and the standard height of the lifting mechanism.

7. The method according to claim 6, characterized in that, The method for obtaining the standard height of the lifting mechanism in which the first super-underride grid layer in the first nuclear fuel assembly is hooked by the grid bars of the second super-underride grid layer in the second nuclear fuel assembly includes: Obtaining the first standard grid height of the first super-underride grid layer in the first nuclear fuel assembly, the second standard grid height of the second super-underride grid layer in the second nuclear fuel assembly, the standard grid length, and the standard coordinates of the lower nozzle; Determining the standard height of the lifting mechanism in which the grid bars of the first nuclear fuel assembly and the second nuclear fuel assembly are hooked based on the first standard grid height, the second standard grid height, the standard grid length, and the standard coordinates of the lower nozzle.

8. A data processing device for a nuclear power plant refueling machine, characterized in that It includes: A first acquisition unit, configured to, in response to a target load operation in a nuclear power plant refueling machine, acquire first load data corresponding to the target load operation from the nuclear power plant refueling machine, where the first load data is collected by a controller in the nuclear power plant refueling machine from multiple data dimensions of the nuclear power plant refueling machine; A second acquisition unit, configured to determine a data acquisition period and acquire second load data during the execution of the target load operation in the nuclear power plant refueling machine based on the data acquisition period; A third acquisition unit, configured to acquire historical load data of a historical load operation corresponding to the target load operation; A mechanical analysis unit, configured to perform a mechanical analysis of the target load operation based on the first load data, the second load data, and the historical load data.

9. An electronic device, comprising a memory and a processor, the memory storing a computer program, characterized in that, When the processor executes the computer program, it implements the nuclear power plant refueling machine data processing method according to any one of claims 1 to 7.

10. A computer-readable storage medium storing a computer program, characterized in that, When the computer program is executed by a processor, it implements the nuclear power plant refueling machine data processing method according to any one of claims 1 to 7.

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