Nuclear power plant virtual control system design method and device based on reliability analysis

Abstract

The invention discloses a nuclear power plant virtual control system design method and device based on reliability analysis. The method comprises the steps of firstly, obtaining a design file of a nuclear power plant control system; then, in simulation software of the nuclear power plant control system, based on a preset control system design criterion, a preliminary virtual control system is constructed according to the design file; next, reliability analysis is carried out on the preliminary virtual control system, and components needing redundancy design are determined according to a reliability analysis result; and finally, generating a final virtual control system according to the components needing redundancy design. According to the nuclear power plant virtual control system design method and device based on reliability analysis provided by the embodiment of the invention, rapid, accurate and efficient reliability analysis can be carried out on the nuclear power plant control system required in the design file based on the virtual control system, so that the rationality and reliability of the design of the nuclear power plant control system are improved; and automatic engineering configuration work can be realized, and the working efficiency is greatly improved.

Description

Technical Field

[0001] The present invention relates to the field of nuclear power technology, and in particular to a method and device for designing a virtual control system of a nuclear power plant based on reliability analysis. Background Art

[0002] As the nerve center of nuclear power plant control, the control system plays an important role in ensuring the safety and reliability of nuclear power plant operation. However, nuclear power plants still have problems with cumbersome processes, low accuracy and efficiency when designing and manufacturing control systems. At present, the design of nuclear power plant control systems is completed through the configuration of digital drawing tools, and when the nuclear power plant provides design information to the control system supplier, the design scheme of the nuclear power plant control system is still submitted to the supplier in the form of design drawings, and then the supplier manually completes the configuration, cabinet allocation and other work, and feedback to the designer in the form of documents. Since the above process is still mainly realized by manual capital raising process, and the digital capital raising process has not yet been opened, it will make it impossible for the supplier to quickly and accurately estimate the number of various modules in the control system, and then the designer will not be able to complete the power consumption, heat dissipation, and layout estimation more accurately, making the overall design work efficiency low. At the same time, multiple rounds of capital raising between the designer and the supplier will cause a waste of manpower and time costs, and is not conducive to ensuring the construction cycle of the nuclear power plant. In addition, in the existing nuclear power plant control system design process, the full path of the control system function signal and functional correlation of the control system are not modeled and reliability analyzed, so it is impossible to accurately design the nuclear power plant control system.

[0003] Patent CN114862275 discloses a reliability assessment method for a warehousing and logistics system based on a digital twin model, including: obtaining attribute parameters of the warehousing and logistics system to establish a digital twin model of the warehousing and logistics system; establishing a real-time data connection between the digital twin model and the warehousing and logistics system to form an equivalent mapping between the warehousing and logistics system and the digital twin model; constructing a fault prediction model to predict faults of the warehousing and logistics system through the digital twin model; and constructing a reliability assessment model to perform reliability status assessment on the operating status of the warehousing and logistics system. Patent CN115496107 discloses a method for analyzing the entire life cycle of an aircraft engine main shaft bearing based on digital twins, including: establishing a digital twin workshop, and establishing a manufacturing process for aircraft engine main shaft bearings based on digital twins on the basis of the digital twin workshop; establishing a digital twin model of aircraft engine main shaft bearings, and real-time monitoring or simulation of the motion state of the main shaft bearings based on multi-parameter data; extracting the vibration signal to be analyzed, and inputting it into the trained artificial neural network after noise reduction processing, and intelligently identifying the fault type of the main shaft bearing; simulating the accelerated fatigue life test of the aircraft engine main shaft bearing, performing life analysis on the test results, and formulating a maintenance strategy for the main shaft bearing. However, the above methods are all based on the establishment of digital twin models for fault analysis based on the already built system, which is not suitable for the design stage of the nuclear power plant control system. Summary of the invention

[0004] The present invention aims to solve one of the above-mentioned technical problems at least to a certain extent.

[0005] To this end, the first purpose of the present invention is to propose a nuclear power plant virtual control system design method based on reliability analysis, which can quickly, accurately and efficiently perform reliability analysis on the nuclear power plant control system in the early design stage of the nuclear power plant control system, thereby improving the rationality and reliability of the nuclear power plant control system design.

[0006] The second object of the present invention is to provide a nuclear power plant virtual control system design device based on reliability analysis.

[0007] To achieve the above-mentioned purpose, the first embodiment of the present invention proposes a method for designing a virtual control system of a nuclear power plant based on reliability analysis, comprising:

[0008] Obtain design documents for nuclear power plant control systems;

[0009] In the simulation software of the nuclear power plant control system, a preliminary virtual control system is constructed according to the design documents based on the preset control system design criteria;

[0010] Conduct reliability analysis on the preliminary virtual control system and determine the components that require redundant design based on the results of the reliability analysis;

[0011] Generate the final virtual control system based on the components that require redundant design.

[0012] Optionally, before obtaining the design documents of the nuclear power plant control system, it also includes:

[0013] Use digital drawing tools to perform functional design of nuclear power plant control systems and generate design documents.

[0014] Optionally, a reliability analysis is performed on the preliminary virtual control system, and components that require redundant design are determined based on the results of the reliability analysis, including:

[0015] Construct a preliminary reliability model of the virtual control system;

[0016] Perform failure mode and effect analysis on the reliability model and identify the fault-related components in the preliminary virtual control system when a single fault with unacceptable fault effect exists in the preliminary virtual control system;

[0017] Design fault-related components redundantly.

[0018] Optionally, a reliability analysis is performed on the preliminary virtual control system, and components that require redundant design are determined based on the results of the reliability analysis, which also includes:

[0019] Conduct fault tree analysis on the reliability model and identify the functions in the preliminary virtual control system that do not meet the preset requirements;

[0020] Identify the most important functional components from those that do not meet the preset requirements;

[0021] Design redundant components for the most important functional parts.

[0022] Optionally, perform a fault tree analysis on the reliability model and identify the functions in the preliminary virtual control system that do not meet the preset requirements, including:

[0023] Determine the reliability index requirements and their corresponding required values ​​for all functions in the preliminary virtual control system;

[0024] When the predicted value of at least one reliability indicator of a certain function is greater than its corresponding required value, it is determined that the function does not meet the preset requirements.

[0025] Optionally, construct a preliminary virtual control system reliability model, including:

[0026] Exporting the functional files of the preliminary virtual control system and importing the functional files into the reliability analysis platform of the nuclear power plant control system, the functional files including at least one of the functional design files, structural design files and functional allocation files;

[0027] A reliability model of the preliminary virtual control system is constructed using the reliability analysis platform.

[0028] Optionally, after the final virtual control system is generated according to the components to be redundantly designed, the following is further included:

[0029] In the simulation software of the nuclear power plant control system, the power consumption and / or heat generation of all components in the final virtual control system are configured, and the power consumption and / or heat generation are used as the upstream input of the design.

[0030] The method for designing a virtual control system of a nuclear power plant based on reliability analysis in an embodiment of the present invention first obtains the design file of the nuclear power plant control system; then, in the simulation software of the nuclear power plant control system, based on the preset control system design criteria, a preliminary virtual control system is constructed according to the design file; next, reliability analysis is performed on the preliminary virtual control system, and components that need redundant design are determined according to the results of the reliability analysis; finally, a final virtual control system is generated according to the components that need redundant design. Therefore, in the design stage of the nuclear power plant control system, the method opens up the flow path of design data, and can perform rapid, accurate and efficient reliability analysis on the nuclear power plant control system required in the design file based on the virtual control system, and perform redundant design of components, thereby improving the rationality and reliability of the design of the nuclear power plant control system, thereby realizing automated engineering configuration work, saving manpower and time costs in the design process of the nuclear power plant, and greatly improving the overall work efficiency.

[0031] To achieve the above-mentioned purpose, the second embodiment of the present invention proposes a nuclear power plant virtual control system design device based on reliability analysis, comprising:

[0032] An acquisition module, used to acquire design documents of nuclear power plant control systems;

[0033] A construction module for constructing a preliminary virtual control system according to design documents based on preset control system design criteria in a simulation software of a nuclear power plant control system;

[0034] A determination module is used to perform reliability analysis on the preliminary virtual control system and determine the components that need redundant design according to the results of the reliability analysis;

[0035] The first generation module is used to generate a final virtual control system according to the components that need redundant design.

[0036] Optionally, the device is characterized in that it also includes:

[0037] The second generation module is used to use digital drawing tools to perform functional design on the nuclear power plant control system and generate design documents.

[0038] Optionally, determine the module for:

[0039] Construct a preliminary reliability model of the virtual control system;

[0040] Perform failure mode and effect analysis on the reliability model and identify the fault-related components in the preliminary virtual control system when a single fault with unacceptable fault effect exists in the preliminary virtual control system;

[0041] Design fault-related components redundantly.

[0042] Optionally, determine the module, also used to:

[0043] Conduct fault tree analysis on the reliability model and identify the functions in the preliminary virtual control system that do not meet the preset requirements;

[0044] Identify the most important functional components from those that do not meet the preset requirements;

[0045] Design redundant components for the most important functional parts.

[0046] Optionally, determine the module, specifically for:

[0047] Determine the reliability index requirements and their corresponding required values ​​for all functions in the preliminary virtual control system;

[0048] When the predicted value of at least one reliability indicator of a certain function is greater than its corresponding required value, it is determined that the function does not meet the preset requirements.

[0049] Optionally, determine the module for:

[0050] Exporting the functional files of the preliminary virtual control system and importing the functional files into the reliability analysis platform of the nuclear power plant control system, the functional files including at least one of the functional design files, structural design files and functional allocation files;

[0051] A reliability model of the preliminary virtual control system is constructed using the reliability analysis platform.

[0052] Optionally, the device further comprises:

[0053] The configuration module is used to configure the power consumption and / or heat generation of all components in the final virtual control system in the simulation software of the nuclear power plant control system, and use the power consumption and / or heat generation as the design upstream input.

[0054] The nuclear power plant virtual control system design device based on reliability analysis of the embodiment of the present invention first obtains the design file of the nuclear power plant control system; then, in the simulation software of the nuclear power plant control system, based on the preset control system design criteria, a preliminary virtual control system is constructed according to the design file; next, reliability analysis is performed on the preliminary virtual control system, and components that need redundant design are determined according to the results of the reliability analysis; finally, a final virtual control system is generated according to the components that need redundant design. Therefore, during the design stage of the nuclear power plant control system, the device opens up the flow path of design data, and can perform rapid, accurate and efficient reliability analysis on the nuclear power plant control system required in the design file based on the virtual control system, and perform redundant design of components, thereby improving the rationality and reliability of the design of the nuclear power plant control system, thereby realizing automated engineering configuration work, saving manpower and time costs in the nuclear power plant design process, and greatly improving overall work efficiency.

[0055] Additional aspects and advantages of the present invention will be given in part in the following description and in part will be obvious from the following description, or will be learned through practice of the present invention. BRIEF DESCRIPTION OF THE DRAWINGS

[0056] The accompanying drawings constituting a part of the present invention are used to provide a further understanding of the present invention. The exemplary embodiments of the present invention and their descriptions are used to explain the present invention and do not constitute an improper limitation of the present invention. In the accompanying drawings:

[0057] Figure 1 A flowchart of a method for designing a virtual control system of a nuclear power plant based on reliability analysis according to an embodiment is presented;

[0058] Figure 2 A flowchart of performing reliability analysis on a preliminary virtual control system and determining components that require redundant design according to the results of the reliability analysis is presented in one embodiment;

[0059] Figure 3 A flowchart of another embodiment of performing reliability analysis on a preliminary virtual control system and determining components that require redundant design based on the results of the reliability analysis is presented;

[0060] Figure 4 A flow chart of a method for designing a virtual control system of a nuclear power plant based on reliability analysis according to another embodiment is shown;

[0061] Figure 5 A flow chart of a method for designing a virtual control system of a nuclear power plant based on reliability analysis according to another embodiment is presented;

[0062] Figure 6 A flowchart of a method for designing a virtual control system for a nuclear power plant based on reliability analysis is presented in a specific embodiment;

[0063] Figure 7 A structural schematic diagram of a nuclear power plant virtual control system design device based on reliability analysis according to an embodiment is presented;

[0064] Figure 8 A structural schematic diagram of a nuclear power plant virtual control system design device based on reliability analysis in another embodiment is presented;

[0065] Fig. 9 A structural schematic diagram of a nuclear power plant virtual control system design device based on reliability analysis of another embodiment is presented. DETAILED DESCRIPTION

[0066] It should be noted that, in the absence of conflict, the embodiments of the present invention and the features in the embodiments can be combined with each other. The present invention will be described in detail below with reference to the accompanying drawings and in combination with the embodiments.

[0067] The present invention is further described in detail below in conjunction with specific embodiments. These embodiments should not be construed as limiting the scope of protection claimed by the present invention.

[0068] The following describes a method and device for designing a virtual control system for a nuclear power plant based on reliability analysis according to an embodiment of the present invention with reference to the accompanying drawings.

[0069] Figure 1 1 is a flow chart of a method for designing a virtual control system of a nuclear power plant based on reliability analysis according to an embodiment of the present invention, which specifically includes the following steps:

[0070] S1, obtain the design documents of the nuclear power plant control system.

[0071] In one embodiment of the present invention, taking the control system of the waste heat removal system of a nuclear power unit as an example, the design documents may include a functional diagram of the control system of the waste heat removal system, a SAMA diagram (a functional block diagram used to represent the control system logic or control strategy based on the regulations of the American Manufacturers Association (SAMA)) and other design documents.

[0072] The above process can obtain the design data of the nuclear power plant control system, thereby providing comprehensive and accurate data support for subsequent design and analysis work.

[0073] S2, in the simulation software of the nuclear power plant control system, a preliminary virtual control system is constructed according to the design documents based on the preset control system design criteria.

[0074] In one embodiment of the present invention, the design file of the nuclear power plant control system obtained in S1 can be imported into the simulation software of the nuclear power plant control system, and a preliminary virtual control system without component redundant design can be constructed based on the preset control system design criteria. The preliminary virtual control system can include functions such as acquisition, processing, output, alarm and monitoring.

[0075] Among them, the preset control system design criteria may include isolation criteria, safety classification criteria, function allocation criteria and subsequent expansion criteria. Specifically, for the isolation criteria, since the execution of column A functions and column B functions in the nuclear power plant control system need not affect each other, the controllers that execute column A functions and column B functions can be set separately when generating the preliminary virtual control system. In addition, in the subsequent configuration work, the corresponding series of power supply cabinets should be selected for the controller. For the safety classification criteria, since the equipment that performs non-safety functions cannot affect the normal operation of the equipment that performs safety functions, if there is signal interaction between the two, isolation equipment can be added to the virtual control system to avoid mutual influence between the two. For the function allocation criteria, in order to reduce the signal interaction between different controllers or control stations to avoid excessive coupling, the system control functions of the same functional group can be allocated to the same controller or control station. For example, since the pressurizer spray valve of the reactor coolant system in the process system corresponding to the nuclear power plant control system is redundantly designed, its control function can be designed in different IO modules of the same controller or the same control station in the preliminary virtual control system. For the subsequent expansion criteria, in order to enable the nuclear power plant control system built according to the virtual control system to be flexibly designed and improved according to the actual scenario in the future, empty slots, such as 20% of empty slots, can be reserved in each control cabinet. For example, the upper limit of the capacity can be designed for each control cabinet in the preliminary virtual control system. If the IO module in a control cabinet reaches the upper limit, the virtual arrangement in this control cabinet is stopped.

[0076] Through the above process, the corresponding preliminary virtual control system can be quickly and conveniently constructed according to the design documents of the nuclear power plant control system, the flow path of the design data in the preliminary virtual control system is opened up, and the nuclear power plant control system required by the design documents is intuitively displayed. At the same time, the functional parameters, configuration and performance indicators of the preliminary virtual control system are consistent with the nuclear power plant control system required in the design documents, and the component attributes in the preliminary virtual control system are consistent with the nuclear power plant control system required in the design documents, which realizes the modeling of the full path and functional correlation of the functional signals of the nuclear power plant control system, thereby making the subsequent analysis process more accurate and effective, and facilitating the subsequent flexible adjustment of the design of the nuclear power plant control system, thereby improving the accuracy and reliability of the design of the nuclear power plant control system.

[0077] S3, conduct reliability analysis on the preliminary virtual control system and determine the components that require redundant design based on the results of the reliability analysis.

[0078] Considering that functions with different importance levels need to be designed with redundancy to different degrees, this embodiment allows functions with different reliability requirements to have redundancy to different degrees through reliability analysis.

[0079] Specifically, the importance levels of functions in the control system are different, and functions with different importance levels should have different reliability requirements. However, redundant design based on design texts and drawings in the prior art will complicate the design process of the control system and require a huge amount of work. In order to improve the overall design work efficiency, this embodiment directly performs reliability analysis on the virtual control system in the early stage of control system design, and based on the results of the reliability analysis, gradually enhances the redundant design of the virtual control system. In addition, considering that redundant design will affect the number of various modules in the control system, this embodiment completes the redundant design before estimating power consumption, heat dissipation, and layout.

[0080] In one embodiment of the present invention, Figure 2 As shown, S3 may include the following steps:

[0081] S31, construct a preliminary reliability model of the virtual control system.

[0082] Specifically, first, the functional files of the preliminary virtual control system are exported from the simulation software of the nuclear power plant control system, and the functional files are imported into the reliability analysis platform of the nuclear power plant control system. Among them, the functional files may include at least one of the functional design files, structural design files, and functional allocation files. Then, the reliability model of the preliminary virtual control system can be constructed using the reliability analysis platform.

[0083] S32, performing failure mode and effect analysis on the reliability model, and when a single fault with unacceptable fault effect exists in the preliminary virtual control system, determining fault-related components in the preliminary virtual control system.

[0084] In one embodiment of the present invention, since the failure of the controller module will cause the entire control station to lose all functions, that is, the impact of its failure is unacceptable, the failure of the controller module is a single failure with unacceptable impact, and the controller module can be determined as a fault-related component in the preliminary virtual control system.

[0085] The above process can perform failure mode and effect analysis on the preliminary virtual control system based on the reliability model, and locate fault-related components quickly, conveniently, efficiently and accurately.

[0086] S33, perform redundant design on fault-related components.

[0087] In one embodiment of the present invention, redundant design is performed on the fault-related components determined in S32. For example, dual standby redundant design can be performed on all controller modules in the control system.

[0088] The above process ensures the safety and reliability of the nuclear power plant control system by designing redundant components related to faults. At the same time, a comprehensive failure mode and impact analysis of the nuclear power plant control system during the design phase can timely adjust the design of the nuclear power plant control system, saving the time and manpower costs of the operation and maintenance of the nuclear power plant control system in subsequent actual operation.

[0089] In another embodiment of the present invention, Figure 4 As shown, after step S31, S3 may further include the following steps:

[0090] S34, performing a fault tree analysis on the reliability model and determining the functions in the preliminary virtual control system that do not meet the preset requirements.

[0091] Specifically, firstly, the reliability index requirements and their corresponding required values ​​of all functions in the preliminary virtual control system are determined.

[0092] In one embodiment of the present invention, the reliability index requirements and their corresponding required values ​​corresponding to each function in the preliminary virtual control system can be determined by the following principles: 1) Reliability index requirements for nuclear power plant control systems in guidelines and standards, such as guideline HAD 102 / 10-2021 and standard GB / T20438; 2) Reliability index requirements expected in previous nuclear power plant control system design plans; 3) Reliability index requirements statistically calculated after the operation of the control system of an in-service nuclear power plant. It is worth noting that the reliability index requirement of a certain function is at least one of unavailability, unreliability, and unconditional failure strength.

[0093] Specifically, if a function has a corresponding reliability index requirement in 1), the reliability index requirement in 1) is determined as the reliability index requirement of the function; if a function does not have a corresponding reliability index requirement in 1), the reliability index requirement in 2) is determined as the reliability index requirement of the function; if a function does not have a corresponding reliability index requirement in 2), the reliability index requirement in 3) is determined as the reliability index requirement of the function.

[0094] Then, the calculated predicted value of the reliability index requirement is compared with the required value. When the predicted value of at least one reliability index of a function is greater than its corresponding required value, it is determined that the function does not meet the preset requirements. For example, the reliability index requirements of a function are unavailability and unreliability, and the required value of unavailability of the function is 10%, and the required value of unreliability is 9.2%. If the calculated predicted value of unavailability of the function is 9.8%, and the predicted value of unreliability is 10%, then since the predicted value of unavailability is greater than its corresponding required value, it is determined that the function does not meet the preset requirements.

[0095] S35, determining the most important functional component from the functions that do not meet the preset requirements.

[0096] In one embodiment of the present invention, if a function does not meet the preset requirements, a reliability index requirement that does not meet the requirements is further selected from the function. Among them, the reliability index requirements include unavailability, unreliability and unconditional failure strength, and the three have a priority order, and the priority of unavailability is higher than the priority of unreliability, which is higher than the priority of unconditional failure strength. If there is only one of the above reliability index requirements that do not meet the requirements, then the reliability index requirement is selected to determine the most important functional component in the function. If there are more than one reliability index requirements that do not meet the requirements, then the reliability index requirement with the highest priority is selected to determine the most important functional component in the function.

[0097] Through the above analysis process, the functions in the preliminary virtual control system that do not meet the preset requirements and the most important functional components in the function can be determined quickly, efficiently and accurately, thereby providing support for the subsequent optimization of the preliminary virtual control system.

[0098] S36, perform redundant design on the most important functional components.

[0099] For example, for the measurement function of key thermal parameters, its reliability index requirements include unavailability, unreliability and unconditional failure strength, and the reliability index requirements that do not meet the requirements selected by S35 include unavailability, unreliability and unconditional failure strength, and it is calculated that the most important functional component in the measurement function is the acquisition card. Therefore, the acquisition card is redundantly designed, and the expected value of the unavailability of the function is recalculated after the redundant design is completed, and it is determined whether the expected value of the unavailability is greater than the corresponding required value. Since the expected value of the unavailability is greater than the corresponding required value, the measurement function does not meet the unavailability requirements, and the most important functional component in the unavailability, such as the acquisition card, is re-determined, and the acquisition card is redundantly designed until the expected value of the unavailability is less than or equal to the corresponding required value.

[0100] Then, after the measurement function meets the unavailability requirement, the predicted value of the reliability index (i.e., unreliability) of the next priority of the measurement function is calculated, and it is determined whether the predicted value of the unreliability is greater than the corresponding required value. It should be understood that the description of redundant design of functional components related to unreliability in the measurement function is consistent with the description of redundant design of functional components related to unavailability in the measurement function, so it will not be repeated.

[0101] Next, after the measurement function meets the unreliability requirement, the predicted value of the reliability index (i.e., unconditional failure strength) of the next priority of the measurement function is calculated, and it is determined whether the predicted value of the unconditional failure strength is greater than the corresponding required value. It should be understood that the description of redundant design of functional components related to unconditional failure strength in the measurement function is consistent with the description of redundant design of functional components related to unavailability in the measurement function, so it will not be repeated.

[0102] Therefore, according to the process flow, operation principles, and process system characteristics of the nuclear power plant, while considering the cabinet configuration capacity and the processing capacity of the processing unit, the partitioning and grouping of the preliminary virtual control system functions can be carried out, and the functional allocation and grouping design schemes of the preliminary virtual control system can be compared to determine the rationality of the preliminary virtual control system design. In addition, by designing redundant functions of the preliminary virtual control system that do not meet the preset requirements and performing repeated iterations, the functions of the nuclear power plant control system adjusted after reliability analysis meet the configuration, thereby ensuring the safety and reliability of the nuclear power plant control system. At the same time, a comprehensive fault tree analysis of the nuclear power plant control system in the design stage can timely adjust the design of the nuclear power plant control system, saving the time and manpower costs of the operation and maintenance of the nuclear power plant control system in the subsequent actual operation.

[0103] S4, generating a final virtual control system based on the components that require redundant design.

[0104] In one embodiment of the present invention, redundant design of relevant functional components is performed through S3, the configuration and structural design of the initial virtual control system are further optimized, a more reasonable and reliable final virtual control system is obtained, a configuration scheme that can be used for a nuclear power plant control system is formed, and it serves as the basis for the nuclear power plant control system to carry out cabinet IO allocation.

[0105] In another embodiment, Figure 4 As shown, before obtaining the design documents of the nuclear power plant control system, it also includes:

[0106] S5, use digital drawing tools to perform functional design of nuclear power plant control systems and generate design documents.

[0107] Specifically, according to the actual design requirements of the nuclear power plant control system, design files are generated through digital drawing tools to open up the data channel between the digital drawing tools and the virtual control system, thereby providing data support for subsequent modeling work.

[0108] In yet another embodiment, Figure 5 As shown, after the final virtual control system is generated according to the components to be redundantly designed, it also includes:

[0109] S6. In the simulation software of the nuclear power plant control system, the power consumption and / or heat generation of all components in the final virtual control system are configured, and the power consumption and / or heat generation are used as the upstream input of the design.

[0110] In one embodiment of the present invention, the design drawing data of the nuclear power plant control system can be downloaded to the final virtual control system, and the power consumption and / or heat generation of all components in the final virtual control system can be configured by utilizing the consistent functional parameters, configuration, performance indicators, etc. of the final virtual control system and the nuclear power plant control system, and the power consumption and / or heat generation of the final virtual control system, as well as the layout, wiring and other data in the final virtual control system are automatically exported as upstream inputs for subsequent designs, thereby quickly and accurately realizing the investment in downstream designs (such as power supply, ventilation, and layout), realizing the automation of engineering configuration work, saving the manpower cost and time cost of the entire nuclear power plant control system design and production integration process, and thus greatly shortening the design cycle of the main control system.

[0111] The method for designing a virtual control system of a nuclear power plant based on reliability analysis in an embodiment of the present invention first obtains the design file of the nuclear power plant control system; then, in the simulation software of the nuclear power plant control system, based on the preset control system design criteria, a preliminary virtual control system is generated according to the design file; next, reliability analysis is performed on the preliminary virtual control system, and components that need redundant design are determined according to the results of the reliability analysis; finally, a final virtual control system is generated according to the components that need redundant design. Therefore, during the design stage of the nuclear power plant control system, the method opens up the flow path of design data, can perform fast, accurate and efficient reliability analysis on the nuclear power plant control system required in the design file based on the virtual control system, and perform redundant design of components, thereby improving the rationality and reliability of the design of the nuclear power plant control system, thereby realizing automated engineering configuration work, saving manpower and time costs in the design process of the nuclear power plant, and greatly improving the overall work efficiency.

[0112] The following is a detailed description of a design method for a virtual control system of a nuclear power plant based on reliability analysis using a specific embodiment.

[0113] In this embodiment, the nuclear power plant control system is the control system of the residual heat removal system of a nuclear power unit. In addition, the virtual nuclear power plant control system in this embodiment includes performance, reliability, power consumption, heat generation, size and configuration data. The virtual nuclear power plant control system is consistent with the functional parameters, configuration, performance indicators, etc. of the physical control system, and the properties of each virtual control system component in the virtual nuclear power plant control system are consistent with the physical control system. At the same time, the virtual nuclear power plant control system includes collection, processing, output, alarm and monitoring functions.

[0114] like Figure 6 As shown, this embodiment specifically includes the following steps:

[0115] S601, use digital drawing tools to complete the functional design of the control system and export the design files of the control system.

[0116] In this embodiment, design files such as a functional diagram and a SAMA diagram of a control system of the waste heat removal system are derived.

[0117] S602, importing the control system design file into the simulation software of the nuclear power plant control system, and constructing a virtual control system without component redundant design based on preset control system design criteria.

[0118] In this embodiment, a virtual control system of the residual heat removal system without redundant control system components is constructed in the simulation software of the nuclear power plant control system.

[0119] S603, exporting the files of the function design, structure design, and function allocation of the virtual control system, and importing them into the control system reliability analysis platform to construct a reliability model of the control system.

[0120] In this embodiment, a reliability model of the control system of the waste heat removal system is constructed in the control system reliability analysis platform.

[0121] S604, performing failure mode and impact analysis on the reliability model of the virtual control system.

[0122] Specifically, if a control system has a single fault whose impact is unacceptable, redundant design is performed for the fault-related control system components.

[0123] In this embodiment, since the failure of a controller module will result in the loss of all functions of the entire control station and the consequences of the failure are unacceptable, all controller modules in the control system adopt a dual standby redundancy design.

[0124] S605, performing a fault tree analysis on the reliability model of the virtual control system.

[0125] Specifically, if the reliability index of the control system function does not meet the requirements, redundant design is performed on the control system components related to the function. This process continuously increases the redundancy until the reliability index requirements of the function are met.

[0126] In this embodiment, because the reliability index of the measurement function of the key thermal parameters cannot meet the requirements, multiple redundancy designs are performed on the relevant acquisition cards.

[0127] S606, complete the redundant design of the virtual control system, generate the final virtual control system, and obtain the number of various components inside the control system.

[0128] In this embodiment, the final number of various components of the control system of the waste heat removal system is obtained.

[0129] S607, determining the power consumption and heat generation of the virtual control system.

[0130] Specifically, the power consumption and heat generation of various components are configured in the simulation software of the nuclear power plant control system, so as to obtain the power consumption and heat generation of the virtual control system as the upstream input of the power supply design and ventilation design of the control system.

[0131] In this embodiment, according to the power consumption and heat generation of the DCS system components actually operating in the nuclear power plant, configuration is performed in the simulation software of the nuclear power plant control system to obtain the power consumption and heat generation of the control system of the waste heat removal system, which serve as the design input for the power supply design and ventilation design of the control system of the waste heat removal system.

[0132] S608, using the virtual control system as an auxiliary tool for control system operation and maintenance.

[0133] In this embodiment, the virtual control system of the residual heat removal system is used as an auxiliary tool for operation and maintenance of the virtual control system of the residual heat removal system after the design of the nuclear power plant control system is completed.

[0134] This specific embodiment specifically describes a method for designing a virtual control system for a nuclear power plant based on reliability analysis, which opens up the data channel between digital drawing tools and control system implementation work, realizes the convenient conversion of electronic design drawings into a virtual control system of corresponding scale, and displays them visually. Based on the configuration of the virtual control system and the characteristics of its components, the reliability analysis of the control system function is carried out, and after repeated iterations, the control system configuration requirements of the virtual control system as the design output are completed. The virtual control system can also be used as an operation and maintenance tool in the actual operation of the subsequent nuclear power plant control system. In addition, the current engineering configuration work is automated, reducing the labor cost and time cost of the entire control system design and production integration process, while greatly shortening the design cycle of the main control system.

[0135] In order to implement the above-mentioned embodiment, the present invention also proposes a reliability design and analysis device for a nuclear power plant control system.

[0136] Figure 7 It is a structural schematic diagram of a nuclear power plant virtual control system design device based on reliability analysis according to an embodiment of the present invention.

[0137] like Figure 7 As shown, the reliability design and analysis device for the control system of a nuclear power plant includes an acquisition module 71 , a construction module 72 , a determination module 73 , and a first generation module 74 .

[0138] The acquisition module 71 is used to acquire the design documents of the nuclear power plant control system.

[0139] The construction module 72 is used to construct a preliminary virtual control system according to the design documents based on the preset control system design criteria in the simulation software of the nuclear power plant control system.

[0140] The determination module 73 is used to perform reliability analysis on the preliminary virtual control system and determine the components that need redundant design according to the results of the reliability analysis.

[0141] Determination module 73 is specifically used to: first, construct a reliability model of the preliminary virtual control system; then, perform failure mode and effect analysis on the reliability model, and when there is a single fault in the preliminary virtual control system with an unacceptable fault impact, determine the fault-related components in the preliminary virtual control system; next, perform redundant design on the fault-related components.

[0142] Specifically, constructing the reliability model of the preliminary virtual control system may include: exporting the functional files of the preliminary virtual control system, and importing the functional files into the reliability analysis platform of the nuclear power plant control system. The functional files may include at least one of the functional design files, the structural design files, and the functional allocation files; and then, constructing the reliability model of the preliminary virtual control system using the reliability analysis platform.

[0143] The determination module 73 is specifically used to: first, perform a fault tree analysis on the reliability model and determine the functions in the preliminary virtual control system that do not meet the preset requirements; then, determine the most important functional components from the functions that do not meet the preset requirements; next, perform redundant design on the most important functional components.

[0144] Among them, a fault tree analysis is performed on the reliability model, and functions in the preliminary virtual control system that do not meet the preset requirements are determined, which may specifically include: determining the reliability index requirements and their corresponding required values ​​for all functions in the preliminary virtual control system, and when the expected value of at least one reliability index of a function is greater than its corresponding required value, determining that the function does not meet the preset requirements.

[0145] The first generating module 74 is used to generate a final virtual control system according to the components that need redundant design.

[0146] In another embodiment, Figure 8 As shown, the device also includes:

[0147] The second generating module 75 is used to perform functional design on the nuclear power plant control system using digital drawing tools and generate design files.

[0148] In yet another embodiment, Fig. 9 As shown, the device also includes:

[0149] The configuration module 76 is used to configure the power consumption and / or heat generation of all components in the final virtual control system in the simulation software of the nuclear power plant control system, and use the power consumption and / or heat generation as the design upstream input.

[0150] It should be understood that the reliability design and analysis device for a nuclear power plant control system is consistent with the description of the corresponding reliability design and analysis method for a nuclear power plant control system, so it will not be described in detail in this embodiment.

[0151] The nuclear power plant virtual control system design device based on reliability analysis of the embodiment of the present invention first obtains the design file of the nuclear power plant control system; then, in the simulation software of the nuclear power plant control system, based on the preset control system design criteria, a preliminary virtual control system is constructed according to the design file; next, reliability analysis is performed on the preliminary virtual control system, and components that need redundant design are determined according to the results of the reliability analysis; finally, a final virtual control system is generated according to the components that need redundant design. Therefore, during the design stage of the nuclear power plant control system, the device opens up the flow path of design data, and can perform rapid, accurate and efficient reliability analysis on the nuclear power plant control system required in the design file based on the virtual control system, and perform redundant design of components, thereby improving the rationality and reliability of the design of the nuclear power plant control system, thereby realizing automated engineering configuration work, saving manpower and time costs in the nuclear power plant design process, and greatly improving overall work efficiency.

[0152] It should be noted that, in this article, relational terms such as first and second, etc. are only used to distinguish one entity or operation from another entity or operation, and do not necessarily require or imply any such actual relationship or order between these entities or operations. Moreover, the terms "include", "comprise" or any other variants thereof are intended to cover non-exclusive inclusion, so that a process, method, article or device including a series of elements includes not only those elements, but also other elements not explicitly listed, or also includes elements inherent to such process, method, article or device. In the absence of further restrictions, the elements defined by the sentence "comprise a ..." do not exclude the existence of other identical elements in the process, method, article or device including the elements.

[0153] It should be noted that, in the description of this specification, the description with reference to the terms "one embodiment", "some embodiments", "example", "specific example", or "some examples" etc. means that the specific features, structures, materials or characteristics described in conjunction with the embodiment or example are included in at least one embodiment or example of the present invention. In this specification, the schematic representations of the above terms do not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials or characteristics described may be combined in any one or more embodiments or examples in a suitable manner. In addition, those skilled in the art may combine and combine the different embodiments or examples described in this specification and the features of the different embodiments or examples, unless they are contradictory.

Claims

1. A method for designing a virtual control system for a nuclear power plant based on reliability analysis, characterized in that: include: Obtain design documents for nuclear power plant control systems; In the simulation software of the nuclear power plant control system, based on preset control system design criteria, a preliminary virtual control system is constructed according to the design document; Performing reliability analysis on the preliminary virtual control system, and determining components that require redundant design based on the results of the reliability analysis; A final virtual control system is generated according to the components requiring redundant design.

2. The method according to claim 1, characterized in that Before obtaining the design documents of the nuclear power plant control system, it also includes: A digital drawing tool is used to perform functional design on the nuclear power plant control system and generate the design file.

3. The method according to claim 1, characterized in that Conduct reliability analysis on the preliminary virtual control system, and determine components that require redundant design based on the results of the reliability analysis, including: Constructing a reliability model of the preliminary virtual control system; Performing a failure mode and effect analysis on the reliability model, and when a single fault with an unacceptable fault effect exists in the preliminary virtual control system, determining the fault-related components in the preliminary virtual control system; Redundancy design is performed on the components related to the fault.

4. The method according to claim 3, characterized in that Performing reliability analysis on the preliminary virtual control system and determining components that require redundant design based on the results of the reliability analysis, further comprising: Performing a fault tree analysis on the reliability model and determining functions in the preliminary virtual control system that do not meet preset requirements; Identify the most important functional components from those that do not meet the preset requirements; The functional components with the highest importance are designed to be redundant.

5. The method according to claim 4, characterized in that Performing a fault tree analysis on the reliability model and determining the functions in the preliminary virtual control system that do not meet the preset requirements, including: Determining reliability index requirements and corresponding required values ​​of all functions in the preliminary virtual control system; When the predicted value of at least one reliability indicator of a certain function is greater than its corresponding required value, it is determined that the function does not meet the preset requirements.

6. The method according to claim 3, characterized in that Constructing a reliability model of the preliminary virtual control system, including: Exporting the functional file of the preliminary virtual control system, and importing the functional file into the reliability analysis platform of the nuclear power plant control system, the functional file including at least one of a functional design file, a structural design file, and a functional allocation file; The reliability analysis platform is used to construct a reliability model of the preliminary virtual control system.

7. The method according to claim 1, characterized in that After generating the final virtual control system according to the components requiring redundant design, the method further includes: In the simulation software of the nuclear power plant control system, the power consumption and / or heating value of all components in the final virtual control system are configured, and the power consumption and / or heating value are used as design upstream input.

8. A virtual control system design device for a nuclear power plant based on reliability analysis, characterized in that: include: An acquisition module, used to acquire design documents of nuclear power plant control systems; A construction module is used to construct a preliminary virtual control system according to the design file in the simulation software of the nuclear power plant control system based on preset control system design criteria; A determination module, used for performing reliability analysis on the preliminary virtual control system and determining components requiring redundant design according to the results of the reliability analysis; The first generating module is used to generate a final virtual control system according to the components requiring redundant design.

9. The device according to claim 8, characterized in that Also includes: The second generating module is used to use a digital drawing tool to perform functional design on the nuclear power plant control system and generate the design file.

10. The device according to claim 8, characterized in that The determining module is used to: Constructing a reliability model of the preliminary virtual control system; Performing a failure mode and effect analysis on the reliability model, and when a single fault with an unacceptable fault effect exists in the preliminary virtual control system, determining the fault-related components in the preliminary virtual control system; Redundancy design is performed on the components related to the fault.

11. The device according to claim 10, characterized in that The determining module is further used for: Performing a fault tree analysis on the reliability model and determining functions in the preliminary virtual control system that do not meet preset requirements; Identify the most important functional components from those that do not meet the preset requirements; The functional components with the highest importance are designed to be redundant.

12. The device according to claim 11, characterized in that The determining module is specifically used for: Determining reliability index requirements and corresponding required values ​​of all functions in the preliminary virtual control system; When the predicted value of at least one reliability indicator of a certain function is greater than its corresponding required value, it is determined that the function does not meet the preset requirements.

13. The device according to claim 10, characterized in that The determining module is used to: Exporting the functional file of the preliminary virtual control system, and importing the functional file into the reliability analysis platform of the nuclear power plant control system, the functional file including at least one of a functional design file, a structural design file, and a functional allocation file; The reliability analysis platform is used to construct a reliability model of the preliminary virtual control system.

14. The device according to claim 8, characterized in that Also includes: A configuration module is used to configure the power consumption and / or heating value of all components in the final virtual control system in the simulation software of the nuclear power plant control system, and use the power consumption and / or heating value as the design upstream input.

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