Verification and test device and method for operation regulation of nuclear power unit, and readable medium

Abstract

The invention provides a verification and test device and method for the operation regulation of a nuclear power unit and a readable medium, and the device comprises a regulation operation system which is used for executing the operation regulation of the nuclear power unit; the verification test system comprises a monitoring module and a data analysis module, the monitoring module is used for collecting key data in the execution process of the nuclear power unit operation regulation in real time, and the key data comprises the equipment state, the operation step, the timestamp and the personnel behavior; and the data analysis module is used for verifying the operation regulation of the nuclear power unit according to the key data, and verifying whether the operation regulation of the nuclear power unit accords with an expected result or not. According to the full-range operation regulation verification and test device based on the regulation operation system, an efficient, accurate and real-time solution is provided for verification and test of power station operation regulation through the characteristics of automatic verification test, real-time monitoring feedback and the like, and the safety and reliability of power station operation are remarkably improved.

Description

Technical Field

[0001] The present invention mainly relates to the field of nuclear power technology, and in particular to a verification and testing device, method and readable medium for operating procedures of a nuclear power unit. Background Art

[0002] In the nuclear power sector, the implementation of nuclear power unit operating procedures is crucial for ensuring the safe, stable, and efficient operation of nuclear power plants. These written procedures guide nuclear power plant operators in performing various operations and monitoring of unit systems, as well as handling system and equipment failures and various accidents. Verifying and testing the effectiveness and reliability of these procedures has become a major challenge for power plant operations management.

[0003] In existing technical solutions, verification and testing of power plant operating procedures are usually carried out through manual review, on-site observation, etc. Although these methods can ensure the correctness of the procedures to a certain extent, they have disadvantages such as low efficiency, lack of accuracy, and poor real-time performance. Specifically, firstly, manual review requires a lot of manpower and time, and is easily affected by human factors, resulting in low efficiency of verification and testing; secondly, on-site observation can often only obtain limited information, which makes it difficult to fully reflect the actual situation of procedure execution, so the accuracy of verification and testing is difficult to guarantee; thirdly, existing technical solutions can usually only perform verification and testing after the procedure is executed, and cannot discover and correct problems in the execution of the procedure in real time, and there is a certain lag. Summary of the Invention

[0004] The technical problem to be solved by the present invention is to provide a verification and testing device, method and readable medium for the operating procedures of nuclear power units, so as to solve the problems of low efficiency, insufficient accuracy and poor real-time performance in manual verification and testing of procedures.

[0005] In order to solve the above technical problems, the present invention provides a verification and testing device for the operating procedures of a nuclear power unit, comprising: a procedure operation system for executing the operating procedures of the nuclear power unit; a verification and testing system, comprising a monitoring module and a data analysis module, wherein the monitoring module is used to collect key data in the execution process of the operating procedures of the nuclear power unit in real time, and the key data include equipment status, operation steps, timestamps, and personnel behavior; the data analysis module is used to verify the operating procedures of the nuclear power unit according to the key data, and verify whether the operating procedures of the nuclear power unit meet the expected results; wherein the data analysis module includes a verification module, and the verification module is used to perform the following verification on the operating procedures of the nuclear power unit according to the key data: functional logic consistency verification, including obtaining a functional analysis list of the operating procedures of the nuclear power unit, performing logical operations on the equipment status after executing the operation steps according to the functional analysis list, and judging whether the logical operations match the design functions, and the functional analysis list divides the nuclear power system into a multi-layer structure, and the multi-layer structure includes overall goals, sub-goals, functions, systems and sub-functions.

[0006] Optionally, the monitoring module includes: a sensor for collecting the equipment status during the execution of the nuclear power unit operating procedures; an audio and video acquisition module for collecting audio and video during the execution of the nuclear power unit operating procedures, the audio and video information including operation steps, timestamps, and personnel behavior; wherein, the data analysis module also includes an audio recognition module and a video recognition module, the audio recognition module is used to recognize the voice in the audio and video into text, and extract the operation steps from the converted text according to the nuclear power professional vocabulary library; the video recognition module is used to identify the personnel behavior from the audio and video based on an image recognition algorithm.

[0007] Optionally, the verification module is also used to perform the following verification on the nuclear power unit operating procedures based on the key data: human-computer interaction verification, including determining whether the operation steps identified by the audio recognition module are consistent with the prescribed steps of the nuclear power unit operating procedures, and determining whether the personnel behavior identified by the video recognition module is consistent with the prescribed behavior of the nuclear power unit operating procedures. If they are consistent, the human-computer interaction verification is passed.

[0008] Optionally, the verification module is also used to perform the following verification on the nuclear power unit operating procedures based on the key data: dynamic simulation verification, including reproducing the accident scenario through a simulator, and inputting the timestamp into the accident scenario to verify the rationality of the procedure timing.

[0009] Optionally, the data analysis module also includes: an intelligent learning and adaptive optimization module, which is used to establish a verification parameter table based on historical verification test data, and the verification parameter table establishes a correspondence between the complexity and criticality of the procedure and the depth and breadth of the verification; the verification module is also used to obtain the corresponding depth and breadth of verification from the verification parameter table according to the complexity and criticality of the nuclear power unit operating procedures, and execute all or part of the verification procedures according to the depth and breadth of the verification.

[0010] Optionally, the data analysis module also includes: a potential problem prediction module, which is used to establish a potential problem prediction model based on historical verification test data, and predict potential problem areas of the nuclear power unit operating procedures through the potential problem prediction model; the verification module is also used to execute all verification procedures on the potential problem areas.

[0011] Optionally, the verification and testing system is a verification and testing platform based on cloud computing, and the verification and testing platform adopts a distributed architecture.

[0012] Optionally, the verification test system further includes an early warning module; the early warning module is configured to send an alarm signal to remind relevant personnel to handle the situation when the data analysis module determines that the operating procedures of the nuclear power unit do not meet expected results.

[0013] In order to solve the above technical problems, the present invention provides a verification and testing method for nuclear power unit operating procedures, including: executing the nuclear power unit operating procedures; collecting key data in the execution process of the nuclear power unit operating procedures in real time, the key data including equipment status, operation steps, timestamps, and personnel behavior; verifying the nuclear power unit operating procedures according to the key data to verify whether the nuclear power unit operating procedures meet the expected results; wherein, the following verification is performed on the nuclear power unit operating procedures according to the key data: functional logic consistency verification, including obtaining a functional analysis list of the nuclear power unit operating procedures, performing logical operations on the equipment status after executing the operation steps according to the functional analysis list, and judging whether the logical operations match the design functions, the functional analysis list divides the nuclear power system into a multi-layer structure, and the multi-layer structure includes overall goals, sub-goals, functions, systems and sub-functions.

[0014] To solve the above technical problems, the present invention provides a computer-readable medium storing computer program code, which, when executed by a processor, implements the verification and testing method for the nuclear power unit operating procedures as described above.

[0015] Compared with the prior art, the present invention has the following advantages:

[0016] The nuclear power unit operating procedure verification and testing device of the present invention features real-time verification capabilities. By collecting and analyzing data and information during procedure execution in real time, the system can promptly identify issues in procedure execution and prevent them from escalating into serious consequences. This real-time monitoring and verification mechanism improves the safety and reliability of power plant operations. Furthermore, the device utilizes automated verification and testing technology, significantly improving verification and testing efficiency and reducing labor costs. BRIEF DESCRIPTION OF THE DRAWINGS

[0017] The accompanying drawings are included to provide a further understanding of the present application, and are incorporated into and constitute a part of this application. The accompanying drawings illustrate embodiments of the present application and, together with this specification, serve to explain the principles of the present invention. In the accompanying drawings:

[0018] Figure 1 The present invention is a system block diagram of a device for verifying and testing the operating procedures of a nuclear power unit according to an embodiment of the present invention.

[0019] Figure 2 yes Figure 1 A system block diagram of a verification and testing device for nuclear power unit operating procedures according to an optimized embodiment.

[0020] Figure 3 The present invention relates to a user interface of a device for verifying and testing the operating procedures of a nuclear power unit according to an embodiment of the present invention.

[0021] Figure 4 The present invention is a flowchart of a method for verifying and testing operating procedures of a nuclear power unit according to an embodiment of the present invention. DETAILED DESCRIPTION

[0022] To more clearly illustrate the technical solutions of the embodiments of this application, the following is a brief introduction to the drawings required for describing the embodiments. Obviously, the drawings described below are merely examples or embodiments of this application. Those skilled in the art can apply this application to other similar scenarios based on these drawings without inventive effort. Unless otherwise apparent from the context or otherwise noted, the same reference numerals in the figures represent the same structure or operation.

[0023] With the rapid development of the power industry and the continuous expansion of power plants, the complexity and accuracy requirements of operating procedures are increasing. In actual power plant operations, various operating procedures (such as GOP / AOP / EOP / POST-72h / SOP / STP / ARP), fire action cards, and temporary operation sheets form the foundation of power plant operations. However, ensuring the accurate execution of these procedures and verifying and testing their effectiveness and reliability have become major challenges in power plant operations management.

[0024] This invention addresses this need and objective: to develop a comprehensive operating procedure verification and testing method based on a procedure-based operating system to ensure accurate implementation of power plant operating procedures and improve the safety and reliability of power plant operations. This invention enables comprehensive verification and testing of power plant operating procedures, effectively preventing safety incidents caused by improper procedure implementation and improving the operational efficiency and management level of power plants.

[0025] Figure 1 FIG. 1 is a system block diagram of a verification and testing device for operating procedures of a nuclear power unit according to an embodiment of the present invention. Figure 1 As shown, the verification and testing device 100 for the operation procedures of a nuclear power unit includes a procedure operation system 1 and a verification and testing system 2. The verification and testing system 2 includes a monitoring module 21 and a data analysis module 22.

[0026] The procedure operation system 1 is used to execute the nuclear power unit operating procedures. The execution monitoring module 21 is used to collect key data during the execution of the nuclear power unit operating procedures in real time, including equipment status, operation steps, timestamps, and personnel behavior. The data analysis module 22 is used to verify the nuclear power unit operating procedures based on the key data to verify whether the nuclear power unit operating procedures meet the expected results.

[0027] In one embodiment of the present invention, the procedure execution system 1 includes the following key modules:

[0028] Task Preparation Module: This module is responsible for viewing the procedure list, creating new tasks, reviewing task order packages, etc. Users can use this module to select the procedure to be executed and configure the corresponding task parameters.

[0029] Temporary operation order module: supports the creation and management of temporary operation order tasks to meet special operation needs.

[0030] Procedure Execution Module: This module is responsible for online and offline execution of procedures, collaborative execution, deviation handling, shift handover, and online audio and video. This module ensures that procedures are executed according to predetermined processes and rules, and provides real-time feedback such as audio and video during execution.

[0031] Result processing module: The execution results will be structured and pushed to the production information system in the form of STP test reports.

[0032] One of the innovative features of this invention is the verification and testing system 2, which utilizes advanced automated verification and testing technologies to monitor and verify the execution of procedures in real time. The monitoring module 21 provides real-time monitoring capabilities to the verification and testing device 100 for nuclear power unit operating procedures. This module accurately collects and processes key data and information during the execution of power plant operating procedures in real time, covering every aspect and key points of the procedure execution process, including but not limited to equipment status, operating procedures, timestamps, and personnel behavior. By collecting data from multiple sources, comprehensive monitoring of the procedure execution process is ensured.

[0033] Data analysis module 22 analyzes and processes the collected data to determine whether the procedure execution meets the expected results. Data analysis module 22 includes verification module 223. Verification module 223 is used to perform human-computer interaction verification, functional logic consistency verification, and dynamic simulation verification of the nuclear power unit operating procedures based on key data.

[0034] 1) Human-computer interaction verification, including judging whether the operation steps are consistent with the steps specified in the nuclear power unit operating procedures, and judging whether the personnel behavior is consistent with the behavior specified in the nuclear power unit operating procedures. If they are consistent, the human-computer interaction verification is passed.

[0035] Nuclear power regulations are implemented with a "zero tolerance" principle. Their stringent nature is reflected in their mandatory compliance, with no steps allowed to be skipped, modified, or reordered without authorization. Major nuclear power accidents, such as Three Mile Island (1979) and Chernobyl (1986), were directly linked to protocol violations: at Three Mile Island, the operator mistakenly closed an emergency cooling water valve (failure to check parameters according to procedures); at Chernobyl, the operator intentionally disabled a safety system during an experiment (a serious violation).

[0036] Currently, nuclear power plant procedures are executed using a two-person monitoring system: the operator verbally provides instructions, and the supervisor verifies the steps and repeats them back for confirmation. However, with numerous procedures to be executed daily, fatigue can lead to errors in the operator's or supervisor's voice, misreading the instructions, or misreading the sequence, which can result in incorrect information being conveyed.

[0037] In one embodiment of the present invention, the monitoring module 21 includes sensors and an audio and video acquisition module. The sensors are used to collect device status during the execution of the nuclear power unit operating procedures. The audio and video acquisition module is used to collect audio and video during the execution of the nuclear power unit operating procedures. The audio and video information includes operation steps, timestamps, and personnel behavior.

[0038] The data analysis module 22 also includes an audio recognition module 221 and a video recognition module 222. The audio recognition module 221 is used to convert speech from audio and video into text and extract operational steps from the converted text based on a nuclear power professional vocabulary library. The verification module 223 compares the operational steps extracted by the audio recognition module 221 with the prescribed steps in the nuclear power unit operating procedures obtained from the procedure operation system 1 to determine whether the two are consistent. If not, the verification fails, indicating that the nuclear power unit operating procedures do not meet the expected results.

[0039] Video recognition module 222 uses an image recognition algorithm to identify personnel behavior from audio and video. For example, it can determine whether the preceding step of isolating related equipment is completed when operating a valve. Verification module 223 compares the personnel behavior identified by video recognition module 222 with the personnel behavior specified in the nuclear power unit operating procedures obtained from procedure operation system 1 to determine whether the two are consistent. If not, verification fails, indicating that the nuclear power unit operating procedures do not meet the expected results.

[0040] 2) Functional logic consistency verification, including obtaining the functional analysis list of the nuclear power unit operating procedures, performing logical operations on the equipment status after executing the operating steps according to the functional analysis list, and judging whether the operation results match the design function. The functional analysis list divides the nuclear power system into a six-layer structure: overall goal → sub-goal → function → system → sub-function.

[0041] In one embodiment, logical operations such as AND operation, OR operation, and NOT operation are performed on the device status of executing operation step 1, operation step 2, and operation step 3. The operation result is the status of the sub-function. For example, the sub-function is the valve opening state. It is determined whether the operation result matches the design function in the functional analysis list. If it does not match, the verification fails and there is a functional logic fault in the current procedure execution.

[0042] For another example, logical operations such as AND, OR, and NOT are performed on the device status of executing operation steps 1, 2, and 3, and the result is the status of the first sub-function; logical operations such as AND, OR, and NOT are performed on the device status of executing operation steps 4, 5, and 6, and the result is the status of the second sub-function; logical operations such as AND, OR, and NOT are then performed on the status of the first sub-function and the status of the second sub-function, and the result is the status of the first system. It is determined whether the status of the first system matches the design function in the energy analysis list. If they do not match, the verification fails, and there is a functional logic fault in the current procedure execution.

[0043] 3) Dynamic simulation verification, including reproducing the accident scenario through a simulator and inputting timestamps into the accident scenario to verify the rationality of the procedure timing.

[0044] In one embodiment, an accident scenario (such as a LOCA loss of coolant accident) is reproduced through a simulator to evaluate the timeliness of the operator's operations under the emergency procedures. LOCA (Loss-of-Coolant Accident) is one of the most serious design basis accidents in nuclear power plants. It refers to a rupture in the primary coolant system that causes continuous loss of coolant, which may cause core meltdown and radioactive release. Nuclear power plants use a high-pressure injection system: injecting boron-containing water at a pressure of >2MPa to compensate for coolant losses in small / medium ruptures. The present invention inputs a timestamp into the LOCA loss of coolant accident, and the simulator tests the time from the occurrence of the rupture to the start-up of the high-pressure injection system. The nuclear power unit operating procedures stipulate that it must be less than 20 seconds to pass the verification. When the startup time is greater than 20 seconds, the verification fails.

[0045] Figure 2 yes Figure 1 System block diagram of the verification and testing device for the nuclear power unit operating procedures of the optimized embodiment. Figure 2 As shown, for the verification and testing device 200 for nuclear power plant operating procedures, the data analysis module 22 also includes an intelligent learning and adaptive optimization module 224. The intelligent learning and adaptive optimization module 224 is used to establish a verification parameter table based on historical verification test data. The verification parameter table establishes a correspondence between the complexity and criticality of the procedure and the depth and breadth of the verification. The verification module 223 is also used to obtain the corresponding verification depth and breadth from the verification parameter table based on the complexity and criticality of the nuclear power plant operating procedures, and automatically execute all or part of the verification procedure based on the depth and breadth of the verification. For example, for nuclear power plant operating procedures with lower complexity and lower criticality, only human-computer interaction verification is performed.

[0046] like Figure 2 As shown, the data analysis module 22 also includes a potential problem prediction module 225. This module is used to establish a potential problem prediction model based on historical verification test data. This model is used to predict potential problem areas within the nuclear power unit's operating procedures. The verification module 223 is also used to execute the entire verification process for these potential problem areas. The present invention can predict potential problem areas based on historical test results and conduct targeted testing.

[0047] Optionally, the verification and testing system 2 also includes an early warning module 23. When the data analysis module 22 determines that the nuclear power unit operating procedures do not meet expected results, the early warning module 23 sends an alarm signal to alert relevant personnel to take corrective action. The system can automatically detect abnormalities during procedure execution, such as equipment failures and operational errors. Once an abnormality is detected, the system immediately triggers an early warning mechanism, highlighting the abnormality and alerting relevant personnel to take corrective action.

[0048] Optionally, the verification and testing system 2 is a cloud computing-based verification and testing platform that utilizes the elastic scalability of cloud computing to handle large-scale verification and testing tasks. Optionally, the verification and testing platform adopts a distributed architecture so that even if some nodes fail, the entire verification and testing platform can still operate normally.

[0049] Optionally, the verification and testing system 2 also includes a visualization module. To facilitate user viewing and understanding of real-time data and information, the system provides a rich set of visualization methods. Through charts, images, and other formats, users can intuitively understand key information such as procedure execution status, equipment operation, and personnel operations.

[0050] Optionally, the verification test system 2 further includes a data storage and backtracking module. The data storage and backtracking module stores the collected data in a database for subsequent data analysis and backtracking. Users can query historical data at any time to understand the history and trend changes of procedure execution.

[0051] Optionally, the verification test system 2 further includes a test report generation module. The test report generation module automatically generates a detailed test report based on the verification test results, providing a basis for subsequent procedure optimization and improvement.

[0052] like Figure 1 As shown, the verification and testing device 100 for the nuclear power unit operating procedures further includes a server 3 and a user interface 4 .

[0053] Server 3 provides auxiliary functions such as user management, permission management, and log viewing. The system uses data encryption, access control, backup and recovery technologies to ensure data security and stable system operation. Through Server 3, administrators can easily manage and authorize users, ensuring system security and stability.

[0054] The user interface 4 is an interactive interface between the user and the system. It adopts an intuitive and friendly design, allowing users to easily view the list of procedures, create new tasks, execute procedures, etc. At the same time, the user interface also provides real-time feedback and alarm prompts to help users understand the status of procedure execution and handle abnormal situations in a timely manner. The user interface is shown in the figure below. Figure 3 shown.

[0055] The present invention provides a full-range operating procedure verification and testing device based on a procedure operation system. Through the collaborative work of the procedure operation system, verification and testing system, server, and user interface, comprehensive, efficient, and accurate verification and testing of power plant operating procedures are achieved. The full-range operating procedure verification and testing device based on a procedure operation system proposed in the present invention has significant advantages and beneficial effects compared to existing technical solutions:

[0056] 1. Real-time

[0057] This system offers powerful real-time monitoring capabilities, providing real-time feedback on protocol execution status and handling of anomalies. By collecting and analyzing data and information during protocol execution, the system can promptly identify and correct issues before they escalate or lead to serious consequences. This real-time monitoring and feedback mechanism improves the safety and reliability of power plant operations.

[0058] 2. Accuracy

[0059] The verification and testing device of this invention aims to ensure the correctness and reliability of procedure execution, using an efficient and meticulous approach to comprehensively verify and test the procedure execution process. This module evaluates key data and information during procedure execution in real time. This method accurately determines whether the procedure execution has achieved the expected results and automatically detects any anomalies, significantly reducing errors and omissions that may be introduced by human factors.

[0060] 3. Efficiency

[0061] This invention utilizes automated verification and testing technology, significantly improving verification and testing efficiency. Traditional manual review and on-site observation methods require significant manpower and time, and are susceptible to human influence. However, the automated verification and testing system of this invention monitors the execution of procedures in real time, automatically collects data, analyzes and processes it, and generates test reports, significantly reducing manpower investment and improving work efficiency.

[0062] 4. Ease of Operation and Scalability

[0063] The user interface of the present invention is intuitive and user-friendly, allowing users to easily view procedure lists, create new tasks, execute procedures, and perform other operations. Furthermore, the system architecture of the present invention has good scalability, allowing for the easy addition of new procedures and test modules to meet the ever-changing and upgrading needs of power plant operation and management.

[0064] 5. Security and Stability

[0065] The server provides auxiliary functions such as user management, role and permission management, and log viewing to ensure system security and stability. Administrators can easily manage and authorize users, preventing unauthorized users from accessing and operating the system. Furthermore, the system log viewing function helps administrators promptly identify and resolve potential security risks.

[0066] Figure 4 FIG. 1 is a flow chart of a method for verifying and testing the operating procedures of a nuclear power unit according to an embodiment of the present invention. Figure 4 As shown, the verification and testing method 400 for nuclear power plant operating procedures includes:

[0067] Step S41: executing the nuclear power unit operating procedures;

[0068] Step S42: Real-time collection of key data during the execution of the nuclear power unit operating procedures, including equipment status, operating steps, timestamps, and personnel behavior;

[0069] Step S43: Automatically verify the nuclear power unit operating procedures based on key data to verify whether the nuclear power unit operating procedures meet expected results.

[0070] Optionally, the automatic verification of the nuclear power unit operating procedures based on the key data includes: human-computer interaction verification, including determining whether the operation steps are consistent with the steps specified in the nuclear power unit operating procedures, and determining whether the personnel behavior is consistent with the behavior specified in the nuclear power unit operating procedures. If they are consistent, the human-computer interaction verification is passed;

[0071] Functional logic consistency verification involves obtaining a functional analysis list of the nuclear power unit's operating procedures, performing logical operations on the equipment status after executing the operating steps based on the functional analysis list, and determining whether the logical operations match the designed functions. The functional analysis list divides the nuclear power system into a six-layer structure: overall goal → sub-goal → function → system → sub-function;

[0072] Dynamic simulation verification includes reproducing the accident scenario through a simulator and inputting timestamps into the accident scenario to verify the rationality of the procedure timing.

[0073] Flowcharts are used in this application to illustrate the operations performed by systems according to embodiments of the present application. It should be understood that the preceding or following operations are not necessarily performed in exact order. Instead, the various steps may be processed in reverse order or simultaneously. Furthermore, other operations may be added to these processes, or one or more operations may be removed from these processes.

[0074] The present application also includes a computer-readable medium storing computer program code, which, when executed by a processor, implements the verification and testing method of the nuclear power unit operating procedures described above.

[0075] When the verification and testing methods of the nuclear power plant operating procedures are implemented as computer programs, they can also be stored in computer-readable storage media as products. For example, computer-readable storage media can include, but are not limited to, magnetic storage devices (e.g., hard disks, floppy disks, magnetic strips), optical disks (e.g., compact disks (CDs), digital versatile disks (DVDs)), smart cards, and flash memory devices (e.g., electrically erasable programmable read-only memories (EPROMs), cards, sticks, key drives). In addition, the various storage media described herein can represent one or more devices and / or other machine-readable media for storing information. The term "machine-readable medium" can include, but is not limited to, wireless channels and various other media (and / or storage media) that can store, contain, and / or carry code and / or instructions and / or data.

[0076] The basic concepts have been described above. It will be apparent to those skilled in the art that the above disclosures are merely illustrative and do not constitute limitations on this application. Although not explicitly stated herein, those skilled in the art may make various modifications, improvements, and amendments to this application. Such modifications, improvements, and amendments are suggested in this application and remain within the spirit and scope of the exemplary embodiments of this application.

[0077] At the same time, this application uses specific terms to describe the embodiments of this application. For example, "one embodiment," "an embodiment," and / or "some embodiments" refer to a certain feature, structure, or characteristic related to at least one embodiment of this application. Therefore, it should be emphasized and noted that "one embodiment," "an embodiment," or "an alternative embodiment" mentioned twice or multiple times in different locations in this specification does not necessarily refer to the same embodiment. In addition, certain features, structures, or characteristics in one or more embodiments of this application may be appropriately combined.

[0078] Some aspects of the present application can be performed entirely by hardware, entirely by software (including firmware, resident software, microcode, etc.), or by a combination of hardware and software. The above hardware or software can be referred to as "data blocks", "modules", "engines", "units", "components" or "systems". The processor can be one or more application-specific integrated circuits (ASICs), digital signal processors (DSPs), digital signal processing devices (DAPDs), programmable logic devices (PLDs), field programmable gate arrays (FPGAs), processors, controllers, microcontrollers, microprocessors or combinations thereof. In addition, various aspects of the present application may be expressed as computer products located in one or more computer-readable media, which include computer-readable program code. For example, computer-readable media may include, but are not limited to, magnetic storage devices (e.g., hard disks, floppy disks, tapes...), optical disks (e.g., compact disks CDs, digital versatile disks DVDs...), smart cards, and flash memory devices (e.g., cards, sticks, key drives...).

[0079] A computer-readable medium may include a propagated data signal embodying computer program code, for example, in baseband or as part of a carrier wave. The propagated signal may be in a variety of forms, including electromagnetic, optical, etc., or a suitable combination thereof. A computer-readable medium may be any computer-readable medium other than a computer-readable storage medium that can be connected to an instruction execution system, apparatus, or device to communicate, propagate, or transmit the program for use. The program code on the computer-readable medium may be transmitted via any suitable medium, including radio, cable, fiber optic cable, radio frequency signal, or similar medium, or any combination of the above.

[0080] Similarly, it should be noted that, in order to simplify the presentation of this application and thus facilitate understanding of one or more embodiments of the invention, the foregoing descriptions of the embodiments of this application sometimes combine multiple features into a single embodiment, figure, or description thereof. However, this disclosure method does not mean that the subject matter of this application requires more features than those recited in the claims. In fact, an embodiment may have fewer features than all of the features of a single embodiment disclosed above.

[0081] As used in this application and the claims, unless the context clearly indicates otherwise, the words "a," "an," "an," and / or "the" are not intended to refer to the singular but may include the plural. Generally speaking, the terms "comprises" and "include" only indicate the inclusion of the steps and elements specifically identified, and these steps and elements do not constitute an exclusive list. A method or apparatus may also include other steps or elements.

[0082] Unless otherwise specifically stated, the relative arrangement of the parts and steps, numerical expressions and numerical values ​​set forth in these embodiments do not limit the scope of the present application. At the same time, it should be understood that, for ease of description, the sizes of the various parts shown in the drawings are not drawn according to actual proportional relationships. The techniques, methods and equipment known to those of ordinary skill in the relevant art may not be discussed in detail, but where appropriate, the techniques, methods and equipment should be considered as part of the authorization specification. In all examples shown and discussed here, any specific values ​​should be interpreted as being merely exemplary and not as limitations. Therefore, other examples of the exemplary embodiments may have different values. It should be noted that similar numbers and letters represent similar items in the following figures, and therefore, once an item is defined in one figure, it does not need to be further discussed in subsequent figures.

[0083] Furthermore, it should be noted that the use of terms such as "first" and "second" to define components is solely for the purpose of distinguishing the corresponding components. Unless otherwise stated, these terms have no special meaning and therefore should not be construed as limiting the scope of protection of this application. Furthermore, while the terms used in this application are selected from commonly known and commonly used terms, some terms mentioned in this specification may have been selected by the applicant at his or her discretion, and their detailed meanings are explained in the relevant sections of this description. Furthermore, this application should be understood not only by the actual terms used, but also by the meaning implied by each term.

[0084] In some embodiments, numbers are used to describe the quantity of components and attributes. It should be understood that such numbers used in the description of the embodiments are modified by the modifiers "about", "approximately" or "substantially" in some examples. Unless otherwise stated, "about", "approximately" or "substantially" indicate that the numbers are allowed to vary by ±20%. Accordingly, in some embodiments, the numerical parameters used in the description and claims are approximate values, which may change according to the required features of individual embodiments. In some embodiments, the numerical parameters should take into account the specified significant digits and adopt the general method of retaining digits. Although the numerical domains and parameters used to confirm the breadth of their range in some embodiments of the present application are approximate values, in specific embodiments, the settings of such numerical values ​​are as accurate as possible within the feasible range.

[0085] Although the present application has been described with reference to the current specific embodiments, ordinary technicians in this technical field should recognize that the above embodiments are only used to illustrate the present application, and various equivalent changes or substitutions can be made without departing from the spirit of the present application. Therefore, as long as the changes and modifications to the above embodiments are within the scope of the essential spirit of the present application, they will fall within the scope of the claims of the present application.

Claims

1. A verification and testing device for nuclear power unit operating procedures, characterized in that: include: Procedure operation system, used to execute nuclear power unit operating procedures; The verification test system includes a monitoring module and a data analysis module. The monitoring module is used to collect key data in real time during the execution of the nuclear power unit operating procedures, wherein the key data includes equipment status, operation steps, timestamps, and personnel behavior; and the data analysis module is used to verify the nuclear power unit operating procedures based on the key data to verify whether the nuclear power unit operating procedures meet expected results. Among them, the data analysis module includes a verification module, which is used to perform the following verification on the nuclear power unit operating procedures based on the key data: functional logic consistency verification, including obtaining a functional analysis list of the nuclear power unit operating procedures, performing logical operations on the equipment status after executing the operating steps according to the functional analysis list, and judging whether the logical operations match the design functions. The functional analysis list divides the nuclear power system into a multi-layer structure, and the multi-layer structure includes overall goals, sub-goals, functions, systems and sub-functions.

2. The verification and testing device for nuclear power unit operating procedures according to claim 1, characterized in that: The monitoring module includes: A sensor for collecting equipment status during the execution of the nuclear power unit operating procedures; An audio and video acquisition module, configured to acquire audio and video during the execution of the nuclear power unit operating procedures, wherein the audio and video information includes operation steps, timestamps, and personnel behavior; Among them, the data analysis module also includes an audio recognition module and a video recognition module. The audio recognition module is used to recognize the voice in the audio and video into text, and extract the operation steps from the converted text according to the nuclear power professional vocabulary library; the video recognition module is used to identify the personnel behavior from the audio and video based on the image recognition algorithm.

3. The verification and testing device for nuclear power unit operating procedures according to claim 2, characterized in that: The verification module is further configured to perform the following verification on the nuclear power unit operating procedures based on the key data: Human-computer interaction verification includes determining whether the operation steps identified by the audio recognition module are consistent with the prescribed steps of the nuclear power unit operating procedures, and determining whether the personnel behavior identified by the video recognition module is consistent with the prescribed behavior of the nuclear power unit operating procedures. If they are consistent, the human-computer interaction verification is passed.

4. The verification and testing device for nuclear power unit operating procedures according to claim 3, characterized in that: The verification module is further configured to perform the following verification on the nuclear power unit operating procedures based on the key data: Dynamic simulation verification includes reproducing the accident scene through a simulator and inputting the timestamp into the accident scene to verify the rationality of the procedure timing.

5. The verification and testing device for nuclear power unit operating procedures according to claim 4, characterized in that: The data analysis module also includes: An intelligent learning and adaptive optimization module for establishing a verification parameter table based on historical verification test data, wherein the verification parameter table establishes a correspondence between the complexity and criticality of the procedure and the depth and breadth of the verification; The verification module is also used to obtain the corresponding verification depth and breadth from the verification parameter table according to the complexity and criticality of the nuclear power unit operating procedures, and execute all or part of the verification procedures according to the verification depth and breadth.

6. The verification and testing device for nuclear power unit operating procedures according to claim 4, characterized in that: The data analysis module also includes: A potential problem prediction module is used to establish a potential problem prediction model based on historical verification test data, and predict potential problem areas of the nuclear power unit operating procedures through the potential problem prediction model; The verification module is further configured to execute a full verification procedure on the potential problem area.

7. The verification and testing device for nuclear power unit operating procedures according to claim 1, characterized in that: The verification and testing system is a verification and testing platform based on cloud computing, and the verification and testing platform adopts a distributed architecture.

8. The verification and testing device for nuclear power unit operating procedures according to claim 1, characterized in that: The verification test system also includes an early warning module; The early warning module is used to send an alarm signal to remind relevant personnel to handle the problem when the data analysis module determines that the operating procedures of the nuclear power unit do not meet the expected results.

9. A method for verifying and testing the operating procedures of a nuclear power unit, characterized in that: include: Implement nuclear power unit operating procedures; Real-time collection of key data during the execution of the nuclear power unit operating procedures, including equipment status, operating steps, timestamps, and personnel behavior; Verifying the operating procedures of the nuclear power unit according to the key data to verify whether the operating procedures of the nuclear power unit meet the expected results; Among them, the following verification is performed on the operating procedures of the nuclear power unit based on the key data: functional logic consistency verification, including obtaining a functional analysis list of the operating procedures of the nuclear power unit, performing logical operations on the equipment status after executing the operating steps according to the functional analysis list, and judging whether the logical operations match the design functions. The functional analysis list divides the nuclear power system into a multi-layer structure, and the multi-layer structure includes overall goals, sub-goals, functions, systems and sub-functions.

10. A computer-readable medium storing computer program code, wherein the computer program code, when executed by a processor, implements the method for verifying and testing nuclear power plant operating procedures according to claim 9.

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