High-temperature gas cooled reactor equipment risk assessment method, device, equipment and storage medium

Abstract

The invention relates to the technical field of nuclear power generation equipment, and discloses a high-temperature gas cooled reactor equipment risk assessment method, device and equipment and a storage medium. In the method, after high-temperature gas cooled reactor operation parameters are obtained, fault data and function modules associated with the fault data are accurately positioned through a fault assessment model; the identification efficiency of fault data is guaranteed, and the high-reliability operation requirement of the high-temperature gas cooled reactor is met; then, in combination with the logic flow chart, a multi-dimensional data screening method is utilized to obtain fault influence equipment related to the fault data, so that comprehensive evaluation on a fault influence range is ensured, and interference of other irrelevant equipment is reduced; and finally, determining priorities and identification colors of different devices by using a preset device division method, and in combination with a pre-constructed visual data model, helping an operator to quickly focus key fault influence devices, and improving the efficiency of positioning the fault devices by the operator, thereby improving the efficiency and accuracy of fault disposal and device risk troubleshooting.

Description

Technical Field

[0001] This invention relates to the field of nuclear power generation equipment technology, specifically to a risk assessment method, apparatus, equipment, and storage medium for high-temperature gas-cooled reactor equipment. Background Technology

[0002] High-temperature gas-cooled reactors (HTGRs) are gas-cooled reactor technologies that use helium as a coolant. They convert nuclear energy into electrical energy through a process that transforms nuclear energy into thermal energy, mechanical energy, and finally electrical energy. Operators monitor and control the entire HTGR system using equipment parameters provided by the DCS system.

[0003] In the risk assessment methods for high-temperature gas-cooled reactor equipment disclosed in related technologies, operators manually consult the high-temperature gas-cooled reactor's operation manual and then conduct a sequential assessment of all the equipment in the reactor. This approach suffers from low assessment efficiency and delayed fault location. Summary of the Invention

[0004] This invention provides a method, apparatus, equipment, and storage medium for risk assessment of high-temperature gas-cooled reactor equipment, in order to solve the problems of low investigation efficiency and delayed fault location in related technologies for risk investigation of high-temperature gas-cooled reactor equipment.

[0005] In a first aspect, the present invention provides a risk assessment method for high-temperature gas-cooled reactor equipment, the method comprising: Based on the collected operating parameters of the high-temperature gas-cooled reactor, the fault data and its associated functional modules are obtained using the trained fault assessment model. The operating parameters of the high-temperature gas-cooled reactor include: high-temperature gas-cooled reactor nuclear measurement data, blower control data, main loop control data, main depressurization loop data, and fuel loading and unloading data. Based on the fault data and its associated functional modules, combined with the logic flowchart, and using a multi-dimensional data filtering method, multiple fault-affected devices were identified. Based on the multiple devices affected by the fault, the priority and corresponding identification color of each device affected by the fault are obtained using a preset device classification method. Based on a pre-built visualization data model, the data model corresponding to each device affected by a fault is marked with a corresponding identification color, and the marked visualization data model is sent to the display screen.

[0006] After obtaining the operating parameters of the high-temperature gas-cooled reactor through the above implementation method, the fault assessment model is used to accurately locate the fault data and its associated functional modules, ensuring the efficiency of fault data identification and meeting the high reliability operation requirements of the high-temperature gas-cooled reactor. Then, combined with the logic flowchart, a multi-dimensional data filtering method is used to obtain the fault-affected equipment related to the fault data, ensuring a comprehensive assessment of the fault impact range and reducing interference from other irrelevant equipment. Finally, the priority and identification color of different equipment are clarified by a preset equipment classification method, combined with a pre-built visualization data model, to help operators quickly focus on key fault-affected equipment, improve the efficiency of operators in locating faulty equipment, and thus improve the efficiency and accuracy of fault handling and equipment risk investigation.

[0007] In one optional implementation, training the fault assessment model includes: Based on the accident analysis, operating technical specifications, probabilistic safety analysis, over-design-baseline accident evaluation, and equipment parameter settings of the high-temperature gas-cooled reactor, feature extraction is performed using a feature extraction model to obtain the safety standards for the high-temperature gas-cooled reactor. Based on the safety standards of the high-temperature gas-cooled reactor, a mapping relationship between the operating parameters of the high-temperature gas-cooled reactor and the safety standards is established, resulting in a safety standard rule base for the high-temperature gas-cooled reactor. Based on the historical operating parameters of the high-temperature gas-cooled reactor and their corresponding functional modules, and combined with the safety standard rule base of the high-temperature gas-cooled reactor, a fault assessment model is obtained by training using fault tree analysis and random forest algorithm.

[0008] Through the above implementation methods, the accident analysis, operational technical specifications, probabilistic safety analysis, over-design-baseline accident evaluation, and equipment parameter settings of the high-temperature gas-cooled reactor are transformed into quantified safety standards using a feature extraction model. Then, by utilizing the mapping relationship between the operating parameters of the high-temperature gas-cooled reactor and the safety standards, the operating parameters are bound to the corresponding safety limits, providing a clear basis for judgment in subsequent model training. Subsequently, by using fault tree analysis and random forest algorithms for training, the propagation path of fault data is sorted out. The random forest algorithm accurately captures the correlation between abnormal operating parameters and fault data, thereby significantly improving the accuracy of fault data identification.

[0009] In one optional implementation, based on the fault data and its associated functional modules, combined with a logic flowchart, a multi-dimensional data filtering method is used to obtain multiple fault-affected devices, including: Based on the functional modules associated with the fault data, the upstream control equipment and the downstream affected equipment are derived using a logic flowchart. Based on the fault data, the correlation coefficient between the fault data and the operating parameters of other equipment is calculated, and equipment with a correlation coefficient greater than a preset threshold is output as fault-related equipment. By combining the upstream control equipment, the downstream affected equipment, and the fault-related equipment, duplicate equipment is eliminated to obtain multiple fault-affected equipment.

[0010] Through the above implementation methods, the fault data propagation link is analyzed by deriving the logic flowchart to ensure that the selected devices conform to the association rules of the functional modules associated with fault data. Then, correlation coefficients are used for correlation analysis to supplement the coupling relationship of data under dynamic operating conditions that cannot be covered by the logic flowchart, ensuring accurate acquisition of fault-affected devices. Finally, the method of eliminating duplicate devices is used to reduce duplicate devices in the final acquired fault-affected devices, avoiding operators from missing important information due to massive amounts of duplicate information, and improving the operator's fault handling efficiency.

[0011] In one optional implementation, the step of obtaining the priority and corresponding identification color of each fault-affected device based on the plurality of fault-affected devices using a preset device classification method includes: For each device affected by a fault, the priority of each affected device is obtained using the priority division method in the device division method; the priority division method includes division based on the safety limits, safety system settings and operating constraints of the high-temperature gas-cooled reactor. Based on the priority of multiple fault-affected devices, the identification color of each fault-affected device is obtained by using the identification color allocation method in the device partitioning method; the identification color allocation method includes the association between priority and corresponding identification color.

[0012] Through the above implementation method, each fault-affected device is divided into its own priority using a priority division method, and then a different identification color is assigned to each priority-affected device using an identification color allocation method. This allows operators to intuitively determine the priority of equipment risk investigation based on the different identification colors, thereby improving the efficiency of operators in investigating equipment risks.

[0013] In one optional implementation, the construction of the visualization data model includes: Based on multiple devices of the high-temperature gas-cooled reactor, a three-dimensional model of the entire high-temperature gas-cooled reactor is obtained by constructing a three-dimensional model; the three-dimensional model includes a cabinet model and internal module models. Based on the operating parameters of the DCS system of the high-temperature gas-cooled reactor, a mapping relationship is established between each operating parameter and each module model of the three-dimensional model to obtain the operating parameter-module association database. Based on the mapping relationship in the operating parameter-module association database, the received current operating parameters of the DCS system are matched with the corresponding module models to obtain a visual data model.

[0014] Through the above implementation methods, the constructed three-dimensional model ensures the simulation of the actual location of the equipment in the high-temperature gas-cooled reactor, laying the foundation for operators to accurately locate the functional modules associated with fault data; then, by using the operating parameter-module association database, the operating parameters of the DCS system of the high-temperature gas-cooled reactor are transformed into intuitive model attributes; and by using the constructed visual data model, the information interpretation cost for operators is reduced, and the accuracy and efficiency of fault handling are improved.

[0015] In one alternative implementation, it further includes: Based on the priority and corresponding identification color of each device affected by a fault, all devices affected by a fault are sorted according to priority to obtain a priority list of devices affected by a fault, and the priority list of devices affected by a fault is sent to the display screen.

[0016] Through the above implementation method, the scattered fault-affected devices are sorted by priority to form a clear priority list, which makes it convenient for operators to quickly focus on the fault-affected devices corresponding to the core risks. It can also more intuitively reflect the overall risk situation of the current high-temperature gas-cooled reactor, provide clear execution order guidance for subsequent risk investigation work, and significantly shorten the overall cycle required from the occurrence of a fault to its handling.

[0017] In one alternative implementation, it further includes: In response to a user's selection action, the system identifies the devices in the area where the user's selection action is located and obtains the target device. Based on the target device, data information about the target device is obtained by filtering from the historical database; the data information includes defect data records, historical data, and maintenance records. Based on the data information of the target device, it is sent to the display screen.

[0018] Through the above implementation method, the data information of the target equipment retrieved from the historical database, which includes defect data records, historical operation data, and maintenance records, is used to display the complete data of the target equipment selected by the user throughout its entire life cycle. This makes it convenient for users to analyze the causes of failures and can further assist operators in judging whether the target equipment has problems of "over-maintenance" or "untimely maintenance", providing complete data support for adjusting maintenance decisions.

[0019] Secondly, the present invention provides a risk assessment device for high-temperature gas-cooled reactor equipment, the device comprising: The fault assessment module is used to obtain fault data and its associated functional modules based on the collected operating parameters of the high-temperature gas-cooled reactor and the trained fault assessment model. The operating parameters of the high-temperature gas-cooled reactor include: high-temperature gas-cooled reactor nuclear measurement data, blower control data, main loop control data, main depressurization loop data, and fuel loading and unloading data. The equipment screening module is used to identify multiple equipment affected by the fault based on the fault data and its associated functional modules, combined with a logic flowchart and a data screening method. The priority division module is used to obtain the priority and corresponding identification color of each fault-affected device based on the multiple fault-affected devices using a preset device division method; The results display module is used to mark the data model corresponding to each fault-affected device with a corresponding identification color based on a pre-built visualization data model, and then send the marked visualization data model to the display screen.

[0020] Thirdly, the present invention provides an electronic device, comprising: a memory and a processor, wherein the memory and the processor are communicatively connected to each other, the memory stores computer instructions, and the processor executes the computer instructions to perform the risk assessment method for high-temperature gas-cooled reactor equipment described in the first aspect or any corresponding embodiment thereof.

[0021] Fourthly, the present invention provides a computer-readable storage medium storing computer instructions for causing a computer to execute the risk assessment method for high-temperature gas-cooled reactor equipment described in the first aspect or any corresponding embodiment thereof. Attached Figure Description

[0022] To more clearly illustrate the specific embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the specific embodiments or the prior art will be briefly introduced below. Obviously, the drawings described below are some embodiments of the present invention. For those skilled in the art, other drawings can be obtained from these drawings without creative effort.

[0023] Figure 1 This is a schematic diagram of an application scenario according to an embodiment of the present invention; Figure 2 This is a schematic diagram of the first process of the risk assessment method for high-temperature gas-cooled reactor equipment according to an embodiment of the present invention; Figure 3 This is a schematic diagram of the second process of the risk assessment method for high-temperature gas-cooled reactor equipment according to an embodiment of the present invention; Figure 4 This is a schematic diagram of the third process of the risk assessment method for high-temperature gas-cooled reactor equipment according to an embodiment of the present invention; Figure 5 This is a schematic diagram of the fourth process of the risk assessment method for high-temperature gas-cooled reactor equipment according to an embodiment of the present invention; Figure 6 This is a structural block diagram of a risk assessment device for high-temperature gas-cooled reactor equipment according to an embodiment of the present invention; Figure 7 This is a schematic diagram of the hardware structure of an electronic device according to an embodiment of the present invention. Detailed Implementation

[0024] To make the objectives, technical solutions, and advantages of the embodiments of the present invention clearer, the technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0025] It is understood that before using the technical solutions disclosed in the various embodiments of the present invention, users should be informed of the types, scope of use, and usage scenarios of the personal information involved in the present invention and their authorization should be obtained in accordance with relevant laws and regulations through appropriate means.

[0026] As an optional application scenario of this invention, such as Figure 1 As shown, application 101 is installed in terminal device 110, and user 130 can interact with application 101 through terminal device 110 and / or access device of terminal device 110.

[0027] For example, application 101 can be any application that provides question-and-answer related services. For instance, application 101 could be a question-and-answer interactive application, such as a text-to-text application, an image-to-text application, etc. Figure 1 In the application scenario shown, if application 101 is active, the terminal device 110 can display the interface 102 of application 101. The interface 102 may include various pages that application 101 can provide, such as interactive pages, settings pages, query pages, etc.

[0028] In some embodiments, terminal device 110 is communicatively connected to server 120 to provide services to application 101. Terminal device 110 may be a mobile terminal, fixed terminal, or portable terminal, etc., including but not limited to mobile phones, desktop computers, laptop computers, multimedia tablets, e-book devices, gaming devices, or any combination thereof, including accessories and peripherals of these devices or any combination thereof. In some embodiments, terminal device 110 may also support any type of interface, and server 120 may be various types of computing systems or servers capable of providing computing power, including but not limited to mainframes, edge computing nodes, computing devices in cloud environments, etc.

[0029] It should be noted that, Figure 1 This is merely an example of an application scenario and does not limit the scope of protection of this invention.

[0030] The embodiments of the present invention will now be described with reference to the accompanying drawings. It should be understood that the pages shown in the drawings are merely examples, and various page designs are possible in practice. The various graphic elements on the page may have different arrangements and different visual representations; one or more elements may be omitted or replaced, and one or more other elements may also be present, without any limitation in the embodiments of the present invention. Furthermore, the embodiments described below primarily pertain to terminal device 110. It should be understood that the actions described relative to terminal device 110 can be performed by application 101 on terminal device 110, or can be performed by application 101 in conjunction with its server (e.g., server 120).

[0031] In the risk assessment methods for high-temperature gas-cooled reactor equipment disclosed in related technologies, operators manually consult the operation manual of the high-temperature gas-cooled reactor and then conduct a sequential inspection of all the equipment in the reactor. However, since the high-temperature gas-cooled reactor contains a large number of cabinet devices and various module devices, and the failure risks and maintenance requirements of different devices are also different, and the corresponding operation manuals contain a lot of information, the risk assessment of equipment by manual inspection is inefficient and the fault location is delayed.

[0032] To address the aforementioned technical issues, this invention provides a risk assessment method for high-temperature gas-cooled reactor (HTGR) equipment. After acquiring HTGR operating parameters, a fault assessment model is used to accurately locate fault data and its associated functional modules, ensuring efficient fault data identification and meeting the high reliability requirements of the HTGR. Then, combined with a logic flowchart, a multi-dimensional data filtering method is used to identify fault-affected devices related to the fault data, ensuring a comprehensive assessment of the fault's impact range and reducing interference from other unrelated devices. Finally, a preset device classification method is used to clarify the priority and identification color of different devices. Combined with a pre-built visualization data model, this helps operators quickly focus on key fault-affected devices, improving the efficiency of fault location and thus enhancing the efficiency and accuracy of fault handling and equipment risk assessment.

[0033] According to an embodiment of the present invention, a method for risk assessment of high-temperature gas-cooled reactor equipment is provided. It should be noted that the steps shown in the flowchart in the accompanying drawings can be executed in a computer system such as a set of computer-executable instructions. Furthermore, although a logical order is shown in the flowchart, in some cases, the steps shown or described may be executed in a different order than that shown here.

[0034] This embodiment provides a risk assessment method for high-temperature gas-cooled reactor equipment, which can be used in the aforementioned nuclear power plant server terminal. Figure 2 This is a flowchart of a risk assessment method for high-temperature gas-cooled reactor equipment according to an embodiment of the present invention, such as... Figure 2 As shown, the process includes the following steps: S201, based on the collected operating parameters of the high-temperature gas-cooled reactor, and using the trained fault assessment model, obtain fault data and its associated functional modules; the operating parameters of the high-temperature gas-cooled reactor include: high-temperature gas-cooled reactor nuclear measurement data, blower control data, main loop control data, main depressurization loop data, and fuel loading and unloading data.

[0035] The operating parameters of a high-temperature gas-cooled reactor (HTGR) include the actual operating parameters of each component during actual operation. HTGR nuclear measurement data includes the reactor source range nuclear power, reactor intermediate range nuclear power, reactor power range nuclear power, and the positive and negative rate of change of reactor nuclear power. Blower control data includes helium hot-end temperature, helium cold-end temperature, main helium flow rate, and main helium blower inverter speed. Main loop control data includes main loop system pressure, main loop system pressure negative rate of change, and main loop humidity. Main pressure relief loop data includes safety valve pressure parameters. Fuel loading and unloading data includes the number of fuel cycle times, the number of fuel element balls in the core, and the core fuel element temperature. The main loop, also known as the primary loop in actual production, is used to ensure the safe and reliable operation of the entire system. The blower control data is obtained based on the operating parameters of the main helium blower.

[0036] Furthermore, the operating parameters of the high-temperature gas-cooled reactor also include: main steam pressure, main steam temperature, main steam valve position, main control valve position, turbine speed, and generator power.

[0037] The trained fault assessment model is an intelligent analysis model trained based on the high-temperature gas-cooled reactor accident analysis report, operating technical specifications, probabilistic safety analysis, over-design baseline accident evaluation and equipment parameter settings, combined with historical operating parameters and corresponding fault cases. Its core function is to identify fault data from the collected operating parameters and obtain the associated functional modules.

[0038] For example, training a fault assessment model includes: Based on the accident analysis, operating technical specifications, probabilistic safety analysis, over-design-baseline accident evaluation, and equipment parameter settings of the high-temperature gas-cooled reactor, feature extraction is performed using a feature extraction model to obtain the safety standards for the high-temperature gas-cooled reactor. Based on the safety standards of the high-temperature gas-cooled reactor, a mapping relationship between the operating parameters of the high-temperature gas-cooled reactor and the safety standards is established, resulting in a safety standard rule base for the high-temperature gas-cooled reactor. Based on the historical operating parameters of the high-temperature gas-cooled reactor and their corresponding functional modules, and combined with the safety standard rule base of the high-temperature gas-cooled reactor, a fault assessment model is obtained by training using fault tree analysis and random forest algorithm.

[0039] S202, based on the fault data and its associated functional modules, combined with the logic flowchart, and using a multi-dimensional data filtering method, multiple fault-affected devices are obtained.

[0040] A logic flowchart is a structured diagram drawn for the overall system and subsystems of a high-temperature gas-cooled reactor. It is used to represent the physical connections, signal transmission, control dependencies, and fault propagation logic between devices or modules.

[0041] Multi-dimensional data filtering methods include using logical deduction and data correlation to filter equipment affected by faults, thereby obtaining equipment affected by faults related to fault data.

[0042] The equipment affected by the fault includes the high-temperature gas-cooled reactor equipment that is directly or indirectly affected by the abnormal events corresponding to the fault data. These are the objects that are subsequently classified and marked according to equipment priority, which directly determines the target and scope of the operator's equipment risk investigation.

[0043] S203, based on the multiple fault-affected devices, using a preset device classification method, obtain the priority and corresponding identification color of each fault-affected device.

[0044] The equipment classification method includes classifying system equipment into different priorities based on the safety limits, safety system settings and operating restrictions in the operating technical specifications of the high-temperature gas-cooled reactor, according to the degree of threat to nuclear safety operation. The identification color refers to the visual identification color that is one-to-one bound to the equipment priority.

[0045] For example, equipment whose current operating conditions immediately and seriously threaten the safe operation of the high-temperature gas-cooled reactor is classified as first priority and identified by the highest level of red; equipment whose current operating conditions do not affect nuclear safety, but which, if left untreated, will deteriorate and indirectly affect the safe operation of the high-temperature gas-cooled reactor, is classified as second priority and identified by orange; equipment whose current operating conditions do not affect the safe operation of the high-temperature gas-cooled reactor is classified as third priority and identified by yellow; and other equipment that is not involved in or affected by the current operating conditions is classified as fourth priority and identified by the lowest level of green.

[0046] S204, based on a pre-built visualization data model, marks the data model corresponding to each fault-affected device with a corresponding identification color, and sends the marked visualization data model to the display screen.

[0047] Visualized data models transform the core elements of a high-temperature gas-cooled reactor, such as physical equipment, control systems, and operating parameters, into visual and interactive digital models, making it easier for operators to locate the equipment in the high-temperature gas-cooled reactor that is subject to risk assessment.

[0048] For example, the construction of a visual data model includes: Based on multiple devices of the high-temperature gas-cooled reactor, a three-dimensional model of the entire high-temperature gas-cooled reactor is obtained by constructing a three-dimensional model; the three-dimensional model includes a cabinet model and internal module models. Based on the operating parameters of the DCS system of the high-temperature gas-cooled reactor, a mapping relationship is established between each operating parameter and each module model of the three-dimensional model to obtain the operating parameter-module association database. Based on the mapping relationship in the operating parameter-module association database, the received current operating parameters of the DCS system are matched with the corresponding module models to obtain a visual data model.

[0049] By matching and fitting the current operating parameters of the DCS system with the constructed module models, and using the mapping relationship, the current operating parameters of the DCS system are stored, processed, and then filled into the cabinet model and internal module model of the entire high-temperature gas-cooled reactor three-dimensional model.

[0050] Each fault-affected device's data model is marked with a corresponding identification color: Based on the digital model of the fault-affected device, visual rendering and labeling are performed according to the identification color bound to its priority. This allows users to intuitively obtain the location of the fault-affected device to be assessed for risk, improving the operator's efficiency in handling fault-affected devices.

[0051] The high-temperature gas-cooled reactor (HTGR) equipment risk assessment method provided in this embodiment obtains the HTGR operating parameters and then uses a fault assessment model to accurately locate fault data and its associated functional modules, ensuring the efficiency of fault data identification and meeting the high reliability operation requirements of the HTGR. Next, combined with a logic flowchart, a multi-dimensional data filtering method is used to identify the fault-affected devices related to the fault data, ensuring a comprehensive assessment of the fault's impact range and reducing interference from other unrelated devices. Finally, a preset device classification method is used to clarify the priority and identification color of different devices, combined with a pre-built visualization data model, to help operators quickly focus on key fault-affected devices, improving the efficiency of fault location and thus enhancing the efficiency and accuracy of fault handling and equipment risk investigation.

[0052] This embodiment provides a risk assessment method for high-temperature gas-cooled reactor equipment, which can be used in the aforementioned nuclear power plant server terminal. Figure 3 This is a flowchart of a risk assessment method for high-temperature gas-cooled reactor equipment according to an embodiment of the present invention, such as... Figure 3 As shown, the process includes the following steps: S301, based on the collected operating parameters of the high-temperature gas-cooled reactor (HTGR), utilizes a trained fault assessment model to obtain fault data and its associated functional modules. The HTGR operating parameters include: HTGR nuclear measurement data, blower control data, main loop control data, main depressurization loop data, and fuel loading / unloading data. For details, please refer to [link to relevant documentation]. Figure 2 S201 of the illustrated embodiment will not be described again here.

[0053] S302, based on the fault data and its associated functional modules, combined with the logic flowchart, and using a multi-dimensional data filtering method, multiple fault-affected devices are obtained.

[0054] Specifically, S302 above includes: S3021, Based on the functional module associated with the fault data, the upstream control equipment and the downstream affected equipment are obtained by deducing using a logic flowchart.

[0055] A logic flowchart is a structured diagram drawn for the overall system and subsystems of a high-temperature gas-cooled reactor. It is used to represent the physical connections, signal transmission, control dependencies, and fault propagation logic between devices or modules.

[0056] Based on the functional modules associated with fault data, the upstream control equipment in the reverse tracing logic flowchart is obtained, and the downstream affected equipment is deduced in the forward deduction. Starting from the functional modules associated with fault data, all equipment related to the fault propagation chain can be fully obtained.

[0057] S3022, Based on the fault data, calculate the correlation coefficient between the fault data and the operating parameters of other devices, and output the devices with a correlation coefficient greater than a preset threshold as fault-related devices.

[0058] By calculating the correlation coefficient between fault data and the operating parameters of other equipment, the implicit relationships between equipment can be captured. This enables the acquisition of equipment whose operating parameters are highly correlated with fault data but do not appear directly in the fault propagation path of the logic flowchart, thereby ensuring comprehensive acquisition of the equipment in the high-temperature gas-cooled reactor related to fault data.

[0059] In this embodiment of the invention, the preset threshold can be implemented as 0.7. By outputting devices with a correlation coefficient greater than 0.7 with fault data as fault-related devices, the probability of omitting devices that do not appear in the logic flowchart can be avoided.

[0060] S3023, combining the upstream control equipment, the downstream affected equipment, and the fault-related equipment, duplicate equipment is eliminated to obtain multiple fault-affected equipment.

[0061] By comprehensively analyzing upstream control equipment, downstream affected equipment, and fault-related equipment, duplicate equipment is eliminated, resulting in a streamlined and non-redundant list of fault-affected equipment. This avoids operators excessively focusing on the same equipment, allowing them to quickly focus on the core fault-affected equipment and shortening the time for troubleshooting and handling.

[0062] S303: Based on the multiple devices affected by the fault, a preset device classification method is used to obtain the priority and corresponding identification color of each affected device. For details, please refer to [link to relevant documentation]. Figure 2 S203 of the illustrated embodiment will not be described again here.

[0063] S304, based on a pre-built visual data model, marks the data model corresponding to each device affected by a fault with a corresponding identification color, and sends the marked visual data model to the display screen. For details, please refer to [link to relevant documentation]. Figure 2 S204 of the illustrated embodiment will not be described again here.

[0064] The high-temperature gas-cooled reactor (HTGR) equipment risk assessment method provided in this embodiment obtains the HTGR operating parameters and then uses a fault assessment model to accurately locate fault data and its associated functional modules, ensuring the efficiency of fault data identification and meeting the high reliability operation requirements of the HTGR. Next, combined with a logic flowchart, a multi-dimensional data filtering method is used to identify the fault-affected devices related to the fault data, ensuring a comprehensive assessment of the fault's impact range and reducing interference from other unrelated devices. Finally, a preset device classification method is used to clarify the priority and identification color of different devices, combined with a pre-built visualization data model, to help operators quickly focus on key fault-affected devices, improving the efficiency of fault location and thus enhancing the efficiency and accuracy of fault handling and equipment risk investigation.

[0065] This embodiment provides a risk assessment method for high-temperature gas-cooled reactor equipment, which can be used in the aforementioned nuclear power plant server terminal. Figure 4 This is a flowchart of a risk assessment method for high-temperature gas-cooled reactor equipment according to an embodiment of the present invention, such as... Figure 4 As shown, the process includes the following steps: S401, based on the collected operating parameters of the high-temperature gas-cooled reactor (HTGR), uses a trained fault assessment model to obtain fault data and its associated functional modules. The HTGR operating parameters include: HTGR nuclear measurement data, blower control data, main loop control data, main depressurization loop data, and fuel loading / unloading data. For details, please refer to [link to relevant documentation]. Figure 2 S201 of the illustrated embodiment will not be described again here.

[0066] S402, based on the aforementioned fault data and its associated functional modules, combined with the logic flowchart, and using a multi-dimensional data filtering method, multiple devices affected by the fault are identified. For details, please refer to [link to relevant documentation]. Figure 2 S202 of the illustrated embodiment will not be described again here.

[0067] S403, based on the multiple fault-affected devices, using a preset device classification method, the priority and corresponding identification color of each fault-affected device are obtained.

[0068] Specifically, S403 includes: S4031, for each device affected by a fault, the priority of each device affected by a fault is obtained by using the priority division method in the device division method; the priority division method includes division using the safety limits, safety system settings and operating restrictions of the high-temperature gas-cooled reactor.

[0069] S4032, based on the priority of multiple fault-affected devices, the identification color of each fault-affected device is obtained by using the identification color allocation method in the device partitioning method; the identification color allocation method includes the association between priority and corresponding identification color.

[0070] By using a priority-based classification method, each fault-affected device is divided into its own priority level. Then, a color-coding method is used to assign different identification colors to each priority level of the fault-affected device. This allows operators to intuitively determine the priority of equipment risk investigation based on the different identification colors, thereby improving the efficiency of operators in investigating equipment risks.

[0071] S404, based on a pre-built visual data model, marks the data model corresponding to each device affected by a fault with a corresponding identification color, and sends the marked visual data model to the display screen. For details, please refer to [link to relevant documentation]. Figure 2 S204 of the illustrated embodiment will not be described again here.

[0072] The high-temperature gas-cooled reactor (HTGR) equipment risk assessment method provided in this embodiment obtains the HTGR operating parameters and then uses a fault assessment model to accurately locate fault data and its associated functional modules, ensuring the efficiency of fault data identification and meeting the high reliability operation requirements of the HTGR. Next, combined with a logic flowchart, a multi-dimensional data filtering method is used to identify the fault-affected devices related to the fault data, ensuring a comprehensive assessment of the fault's impact range and reducing interference from other unrelated devices. Finally, a preset device classification method is used to clarify the priority and identification color of different devices, combined with a pre-built visualization data model, to help operators quickly focus on key fault-affected devices, improving the efficiency of fault location and thus enhancing the efficiency and accuracy of fault handling and equipment risk investigation.

[0073] This embodiment provides a risk assessment method for high-temperature gas-cooled reactor equipment, which can be used in the aforementioned nuclear power plant server terminal. Figure 5 This is a flowchart of a risk assessment method for high-temperature gas-cooled reactor equipment according to an embodiment of the present invention, such as... Figure 5 As shown, the process includes the following steps: S501, based on the collected operating parameters of the high-temperature gas-cooled reactor (HTGR), uses a trained fault assessment model to obtain fault data and its associated functional modules. The HTGR operating parameters include: HTGR nuclear measurement data, blower control data, main loop control data, main depressurization loop data, and fuel loading / unloading data. For details, please refer to [link to relevant documentation]. Figure 2 S201 of the illustrated embodiment will not be described again here.

[0074] S502, based on the aforementioned fault data and its associated functional modules, combined with the logic flowchart, and using a multi-dimensional data filtering method, multiple devices affected by the fault are identified. For details, please refer to [link to relevant documentation]. Figure 2 S202 of the illustrated embodiment will not be described again here.

[0075] S503: Based on the multiple devices affected by the fault, a preset device classification method is used to obtain the priority and corresponding identification color of each affected device. For details, please refer to [link to relevant documentation]. Figure 2 S203 of the illustrated embodiment will not be described again here.

[0076] S504, based on a pre-built visual data model, marks the data model corresponding to each device affected by a fault with a corresponding identification color, and sends the marked visual data model to the display screen. For details, please refer to [link to relevant documentation]. Figure 2 S204 of the illustrated embodiment will not be described again here.

[0077] S505, based on the priority and corresponding identification color of each fault-affected device, sort all fault-affected devices according to priority to obtain a priority list of fault-affected devices, and send the priority list of fault-affected devices to the display screen.

[0078] The marked devices affected by the faults are sorted by priority, and a list is generated and displayed on the display interface of the cabinet function module of the visualization system. The devices with the highest priority, the greatest threat to nuclear safety, and requiring immediate handling are placed at the top of the list for emphasis; the remaining devices with decreasing priority are arranged in order, with clear hierarchy, providing a strong basis for subsequent fault investigation and handling.

[0079] By prioritizing the devices affected by scattered faults, a clear priority list is formed, which makes it easier for operators to quickly focus on the devices affected by faults corresponding to core risks. It also provides a more intuitive reflection of the overall risk situation of the high-temperature gas-cooled reactor, and provides clear execution order guidance for subsequent risk investigation work, which significantly shortens the overall cycle required from the occurrence of a fault to its resolution.

[0080] Furthermore, the risk assessment method for high-temperature gas-cooled reactor equipment provided in this embodiment of the invention also includes: In response to a user's selection action, the system identifies the devices in the area where the user's selection action is located and obtains the target device. Based on the target device, data information about the target device is obtained by filtering from the historical database; the data information includes defect data records, historical data, and maintenance records. Based on the data information of the target device, it is sent to the display screen.

[0081] For example, when a user selects an action, the system dynamically displays the target device's data information on the screen in response to the user's action. Examples include: historical defect data records, which trace past defects of the cabinet's functional modules, including the time of occurrence, symptoms, handling measures, and results, facilitating operators to summarize experience and prevent similar defects; historical data trend charts, which graphically present the trends of key parameters over time, enabling operators to promptly identify abnormal fluctuations and predict potential faults; module preventative maintenance records, which record maintenance plans, times, content, and maintenance personnel, assisting operators in rationally scheduling maintenance and ensuring proper equipment operation; and a floor plan showing the cabinet's location within the factory building and its surrounding environment, facilitating quick location and on-site inspection by operators.

[0082] By utilizing data information from the target equipment retrieved from the historical database, including defect data records, historical operating data, and maintenance records, the system displays complete data for the entire lifecycle of the target equipment selected by the user. This facilitates the user's analysis of the causes of failures and further assists operators in determining whether the target equipment has issues of "over-maintenance" or "untimely maintenance," providing comprehensive data support for adjusting maintenance decisions.

[0083] The high-temperature gas-cooled reactor (HTGR) equipment risk assessment method provided in this embodiment obtains the HTGR operating parameters and then uses a fault assessment model to accurately locate fault data and its associated functional modules, ensuring the efficiency of fault data identification and meeting the high reliability operation requirements of the HTGR. Next, combined with a logic flowchart, a multi-dimensional data filtering method is used to identify the fault-affected devices related to the fault data, ensuring a comprehensive assessment of the fault's impact range and reducing interference from other unrelated devices. Finally, a preset device classification method is used to clarify the priority and identification color of different devices, combined with a pre-built visualization data model, to help operators quickly focus on key fault-affected devices, improving the efficiency of fault location and thus enhancing the efficiency and accuracy of fault handling and equipment risk investigation.

[0084] This embodiment also provides a risk assessment device for high-temperature gas-cooled reactor equipment. This device is used to implement the above embodiments and preferred embodiments, and details already described will not be repeated. As used below, the term "module" can be a combination of software and / or hardware that performs a predetermined function. Although the device described in the following embodiments is preferably implemented in software, hardware implementation, or a combination of software and hardware, is also possible and contemplated.

[0085] This embodiment provides a risk assessment device for high-temperature gas-cooled reactor equipment, such as... Figure 6 As shown, it includes: The fault assessment module 610 is used to obtain fault data and its associated functional modules based on the collected operating parameters of the high-temperature gas-cooled reactor and the trained fault assessment model. The operating parameters of the high-temperature gas-cooled reactor include: high-temperature gas-cooled reactor nuclear measurement data, blower control data, main loop control data, main depressurization loop data, and fuel loading and unloading data. The equipment screening module 620 is used to obtain multiple equipment affected by the fault based on the fault data and its associated functional modules, combined with a logic flowchart and a data screening method. The priority division module 630 is used to obtain the priority and corresponding identification color of each fault-affected device based on the multiple fault-affected devices using a preset device division method; The results display module 640 is used to mark the data model corresponding to each fault-affected device with a corresponding identification color based on a pre-built visualization data model, and send the marked visualization data model to the display screen.

[0086] In some alternative implementations, it also includes: Fault model training unit 650 is specifically used for: Based on the accident analysis, operating technical specifications, probabilistic safety analysis, over-design-baseline accident evaluation, and equipment parameter settings of the high-temperature gas-cooled reactor, feature extraction is performed using a feature extraction model to obtain the safety standards for the high-temperature gas-cooled reactor. Based on the safety standards of the high-temperature gas-cooled reactor, a mapping relationship between the operating parameters of the high-temperature gas-cooled reactor and the safety standards is established, resulting in a safety standard rule base for the high-temperature gas-cooled reactor. Based on the historical operating parameters of the high-temperature gas-cooled reactor and their corresponding functional modules, and combined with the safety standard rule base of the high-temperature gas-cooled reactor, a fault assessment model is obtained by training using fault tree analysis and random forest algorithm.

[0087] In some alternative implementations, the device screening module 620 includes: The first screening unit 6201 is used to deduce the upstream control equipment and the downstream affected equipment by using a logic flowchart based on the functional module associated with the fault data. The second filtering unit 6202 is used to calculate the correlation coefficient between the fault data and the operating parameters of other equipment based on the fault data, and output the equipment with a correlation coefficient greater than a preset threshold as fault-related equipment. The equipment aggregation unit 6203 is used to integrate the upstream control equipment, the downstream affected equipment, and the fault-related equipment, and to remove duplicate equipment to obtain multiple fault-affected equipment.

[0088] In some alternative implementations, the priority division module 630 includes: The priority determination unit 6301 is used to determine the priority of each affected device by using the priority division method in the device division method for each affected device; the priority division method includes division using the safety limits, safety system settings and operating restrictions of the high-temperature gas-cooled reactor. The identification color allocation unit 6302 is used to obtain the identification color of each fault-affected device based on the priority of multiple fault-affected devices and using the identification color allocation method in the device division method; the identification color allocation method includes the association relationship between priority and corresponding identification color.

[0089] In some alternative implementations, a model building module 660 is also included, for: Based on multiple devices of the high-temperature gas-cooled reactor, a three-dimensional model of the entire high-temperature gas-cooled reactor is obtained by constructing a three-dimensional model; the three-dimensional model includes a cabinet model and internal module models. Based on the operating parameters of the DCS system of the high-temperature gas-cooled reactor, a mapping relationship is established between each operating parameter and each module model of the three-dimensional model to obtain the operating parameter-module association database. Based on the mapping relationship in the operating parameter-module association database, the received current operating parameters of the DCS system are matched with the corresponding module models to obtain a visual data model.

[0090] In some optional implementations, a priority list display unit is also included, used for: Based on the priority and corresponding identification color of each device affected by a fault, all devices affected by a fault are sorted according to priority to obtain a priority list of devices affected by a fault, and the priority list of devices affected by a fault is sent to the display screen.

[0091] In some alternative implementations, a data interaction module 670 is also included, for: In response to a user's selection action, the system identifies the devices in the area where the user's selection action is located and obtains the target device. Based on the target device, data information about the target device is obtained by filtering from the historical database; the data information includes defect data records, historical data, and maintenance records. Based on the data information of the target device, it is sent to the display screen.

[0092] The high-temperature gas-cooled reactor equipment risk assessment device provided in this embodiment of the invention can execute the high-temperature gas-cooled reactor equipment risk assessment method provided in any embodiment of the invention, and has the corresponding functional modules and beneficial effects for executing the method. Further functional descriptions of the above modules and units are the same as in the corresponding embodiments described above, and will not be repeated here.

[0093] Figure 7 This is a schematic diagram of the structure of an electronic device provided in an embodiment of the present invention.

[0094] The following is a detailed reference. Figure 7 This diagram illustrates a suitable structural schematic for implementing an electronic device according to embodiments of the present invention. The electronic device may include a processor (e.g., a central processing unit, graphics processor, etc.) 701, which can perform various appropriate actions and processes based on a program stored in read-only memory (ROM) 702 or a program loaded from memory 708 into random access memory (RAM) 703. The RAM 703 also stores various programs and data required for the operation of the electronic device. The processor 701, ROM 702, and RAM 703 are interconnected via a bus 704. An input / output (I / O) interface 705 is also connected to the bus 704.

[0095] Typically, the following devices can be connected to I / O interface 705: input devices 706 including, for example, touchscreens, touchpads, keyboards, mice, cameras, microphones, accelerometers, gyroscopes, etc.; output devices 707 including, for example, liquid crystal displays (LCDs), speakers, vibrators, etc.; memory devices 708 including, for example, magnetic tapes, hard disks, etc.; and communication devices 709. Communication device 709 allows electronic devices to exchange data via wireless or wired communication with other devices. Although Figure 7 Electronic devices with various devices are shown, but it should be understood that it is not required to implement or have all of the devices shown, and more or fewer devices may be implemented or have instead.

[0096] In particular, according to embodiments of the present invention, the processes described above with reference to the flowcharts can be implemented as computer software programs. For example, embodiments of the present invention include a computer program product comprising a computer program carried on a non-transitory computer-readable medium, the computer program containing program code for performing the methods shown in the flowcharts. In such embodiments, the computer program can be downloaded and installed from a network via a communication device 709, or installed from a memory 708, or installed from a ROM 702. When the computer program is executed by the processor 701, it performs the functions defined in the high-temperature gas-cooled reactor equipment risk assessment method of the embodiments of the present invention.

[0097] Figure 7 The electronic device shown is merely an example and should not be construed as limiting the functionality and scope of use of the embodiments of the present invention.

[0098] This invention also provides a computer-readable storage medium. The methods described above according to embodiments of the invention can be implemented in hardware or firmware, or implemented as computer code that can be recorded on a storage medium, or implemented as computer code downloaded via a network and originally stored on a remote storage medium or a non-transitory machine-readable storage medium and then stored on a local storage medium. Thus, the methods described herein can be processed by software stored on a storage medium using a general-purpose computer, a dedicated processor, or programmable or dedicated hardware. The storage medium can be a magnetic disk, optical disk, read-only memory, random access memory, flash memory, hard disk, or solid-state drive, etc.; further, the storage medium can also include combinations of the above types of memory. It is understood that computers, processors, microprocessor controllers, or programmable hardware include storage components capable of storing or receiving software or computer code. When the software or computer code is accessed and executed by the computer, processor, or hardware, the high-temperature gas-cooled reactor equipment risk assessment method shown in the above embodiments is implemented.

[0099] A portion of this invention can be applied as a computer program product, such as computer program instructions, which, when executed by a computer, can invoke or provide the methods and / or technical solutions according to the invention through the operation of the computer. Those skilled in the art will understand that the forms in which computer program instructions exist in a computer-readable medium include, but are not limited to, source files, executable files, installation package files, etc. Correspondingly, the ways in which computer program instructions are executed by a computer include, but are not limited to: the computer directly executing the instructions, or the computer compiling the instructions and then executing the corresponding compiled program, or the computer reading and executing the instructions, or the computer reading and installing the instructions and then executing the corresponding installed program. Here, the computer-readable medium can be any available computer-readable storage medium or communication medium accessible to a computer.

[0100] Although embodiments of the invention have been described in conjunction with the accompanying drawings, those skilled in the art can make various modifications and variations without departing from the spirit and scope of the invention, and such modifications and variations all fall within the scope defined by the appended claims.

Claims

1. A risk assessment method for high-temperature gas-cooled reactor equipment, characterized in that, The method includes: Based on the collected operating parameters of the high-temperature gas-cooled reactor, the fault data and its associated functional modules are obtained using the trained fault assessment model. The operating parameters of the high-temperature gas-cooled reactor include: high-temperature gas-cooled reactor nuclear measurement data, blower control data, main loop control data, main depressurization loop data, and fuel loading and unloading data. Based on the fault data and its associated functional modules, combined with the logic flowchart, and using a multi-dimensional data filtering method, multiple fault-affected devices were identified. Based on the multiple devices affected by the fault, the priority and corresponding identification color of each device affected by the fault are obtained using a preset device classification method. Based on a pre-built visualization data model, the data model corresponding to each device affected by a fault is marked with a corresponding identification color, and the marked visualization data model is sent to the display screen.

2. The method according to claim 1, characterized in that, The training of the fault assessment model includes: Based on the accident analysis, operating technical specifications, probabilistic safety analysis, over-design-baseline accident evaluation, and equipment parameter settings of the high-temperature gas-cooled reactor, feature extraction is performed using a feature extraction model to obtain the safety standards for the high-temperature gas-cooled reactor. Based on the safety standards of the high-temperature gas-cooled reactor, a mapping relationship between the operating parameters of the high-temperature gas-cooled reactor and the safety standards is established, resulting in a safety standard rule base for the high-temperature gas-cooled reactor. Based on the historical operating parameters of the high-temperature gas-cooled reactor and their corresponding functional modules, and combined with the safety standard rule base of the high-temperature gas-cooled reactor, a fault assessment model is obtained by training using fault tree analysis and random forest algorithm.

3. The method according to claim 1, characterized in that, Based on the fault data and its associated functional modules, combined with a logic flowchart, and using a multi-dimensional data filtering method, multiple devices affected by the fault are identified, including: Based on the functional modules associated with the fault data, the upstream control equipment and the downstream affected equipment are derived using a logic flowchart. Based on the fault data, the correlation coefficient between the fault data and the operating parameters of other equipment is calculated, and equipment with a correlation coefficient greater than a preset threshold is output as fault-related equipment. By combining the upstream control equipment, the downstream affected equipment, and the fault-related equipment, duplicate equipment is eliminated to obtain multiple fault-affected equipment.

4. The method according to claim 1, characterized in that, Based on the multiple fault-affected devices, a preset device classification method is used to obtain the priority and corresponding identification color of each fault-affected device, including: For each device affected by a fault, the priority of each affected device is obtained using the priority division method in the device division method; the priority division method includes division based on the safety limits, safety system settings and operating constraints of the high-temperature gas-cooled reactor. Based on the priority of multiple fault-affected devices, the identification color of each fault-affected device is obtained by using the identification color allocation method in the device partitioning method; the identification color allocation method includes the association between priority and corresponding identification color.

5. The method according to claim 1, characterized in that, The construction of the visualization data model includes: Based on multiple devices of the high-temperature gas-cooled reactor, a three-dimensional model of the entire high-temperature gas-cooled reactor is obtained by constructing a three-dimensional model; the three-dimensional model includes a cabinet model and internal module models. Based on the operating parameters of the DCS system of the high-temperature gas-cooled reactor, a mapping relationship is established between each operating parameter and each module model of the three-dimensional model to obtain the operating parameter-module association database. Based on the mapping relationship in the operating parameter-module association database, the received current operating parameters of the DCS system are matched with the corresponding module models to obtain a visual data model.

6. The method according to claim 1, characterized in that, Also includes: Based on the priority and corresponding identification color of each device affected by a fault, all devices affected by a fault are sorted according to priority to obtain a priority list of devices affected by a fault, and the priority list of devices affected by a fault is sent to the display screen.

7. The method according to claim 1, characterized in that, Also includes: In response to a user's selection action, the system identifies the devices in the area where the user's selection action is located and obtains the target device. Based on the target device, data information about the target device is obtained by filtering from the historical database; the data information includes defect data records, historical data, and maintenance records. Based on the data information of the target device, it is sent to the display screen.

8. A risk assessment device for high-temperature gas-cooled reactor equipment, characterized in that, The device includes: The fault assessment module is used to obtain fault data and its associated functional modules based on the collected operating parameters of the high-temperature gas-cooled reactor and the trained fault assessment model. The operating parameters of the high-temperature gas-cooled reactor include: high-temperature gas-cooled reactor nuclear measurement data, blower control data, main loop control data, main depressurization loop data, and fuel loading and unloading data. The equipment screening module is used to identify multiple equipment affected by the fault based on the fault data and its associated functional modules, combined with a logic flowchart and a data screening method. The priority division module is used to obtain the priority and corresponding identification color of each fault-affected device based on the multiple fault-affected devices using a preset device division method; The results display module is used to mark the data model corresponding to each fault-affected device with a corresponding identification color based on a pre-built visualization data model, and then send the marked visualization data model to the display screen.

9. An electronic device, characterized in that, include: A memory and a processor are interconnected, the memory stores computer instructions, and the processor executes the computer instructions to perform the risk assessment method for high-temperature gas-cooled reactor equipment as described in any one of claims 1 to 7.

10. A computer-readable storage medium, characterized in that, The computer-readable storage medium stores computer instructions for causing the computer to execute the risk assessment method for high-temperature gas-cooled reactor equipment as described in any one of claims 1 to 7.

Images