Fault analysis method and system based on virtual DCS

The fault analysis system of virtual DCS enables automated simulation and impact monitoring of fault points in nuclear power plants, solving the problem of low efficiency in manual diagnosis and improving the accuracy and safety of fault analysis.

CN121857656APending Publication Date: 2026-04-14YANGJIANG NUCLEAR POWER +1
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Patent Information

Authority / Receiving Office
CN · China
Patent Type
Applications(China)
Current Assignee / Owner
Filing Date
2026-02-11
Publication Date
2026-04-14

AI Technical Summary

Technical Problem

In existing technologies, fault analysis of instrumentation and control systems in nuclear power plants relies on manual diagnosis, which increases the workload of maintenance personnel, reduces efficiency, and poses a risk of human error, thus affecting the safe operation of nuclear power plants.

Method used

A fault analysis method and system based on virtual DCS is adopted. Through automated simulation of injection equipment, nuclear power simulation platform and extrapolation analysis equipment, the fault point is located and the scope of impact is monitored, including fault data injection, simulation execution and monitoring result analysis.

Benefits of technology

It has improved the efficiency and accuracy of nuclear power plant fault analysis, shortened fault diagnosis time, ensured the safe operation of nuclear power plants, and reduced the risk of human error.

✦ Generated by Eureka AI based on patent content.

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Patent Text Reader

Abstract

The invention discloses a fault analysis method and system based on a virtual DCS, the method is applied to a fault analysis system, and the fault analysis system comprises an injection device, a deduction analysis device and a nuclear power simulation platform based on the virtual DCS. The DCS fault data are sent to the injection equipment, the DCS fault data comprise fault points, monitoring variables and deduction time, the injection equipment generates fault variables, control instructions and monitoring instructions according to the fault points and the deduction time, and the fault variables and the control instructions are sent to the nuclear power simulation platform; the monitoring variable and the monitoring instruction are sent to the deduction analysis equipment, the nuclear power simulation platform executes simulation according to the fault variable and the control instruction, and the deduction analysis equipment monitors the simulation process of the nuclear power simulation platform according to the monitoring variable and the monitoring instruction to obtain a monitoring result corresponding to the monitoring variable. The efficiency of nuclear power plant fault analysis and the accuracy of a fault analysis result are improved.
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Description

Technical Field

[0001] This invention relates to the field of nuclear power simulation technology, and in particular to a fault analysis method and system based on virtual DCS. Background Technology

[0002] During the operation of the instrumentation and control system in a nuclear power plant, malfunctions, defects, or unreasonable system parameter settings in equipment or components often lead to abnormalities in the instrumentation and control system. Currently, the traditional instrumentation and control maintenance method mainly involves relevant maintenance personnel analyzing and diagnosing the faults one by one based on their professional knowledge and skills after a fault occurs. With the expansion of the scale and complexity of nuclear power plants, relying solely on manual fault analysis and diagnosis increases the workload of maintenance personnel to a certain extent and limits the efficiency of maintenance work. In the process of maintenance, the fatigue and negligence of maintenance personnel may also increase the risk of human error, thereby threatening the safe operation of the nuclear power plant.

[0003] Therefore, how to comprehensively analyze the impact range of nuclear power plant failure points and improve the efficiency of nuclear power plant failure analysis has become an urgent problem to be solved. Summary of the Invention

[0004] Based on this, a fault analysis method and system based on virtual DCS is provided to solve the problem of how to comprehensively analyze the impact range of fault points in nuclear power plants and improve the efficiency of fault analysis in nuclear power plants.

[0005] In a first aspect, embodiments of the present invention provide a fault analysis method based on a virtual DCS. The fault analysis method is applied to a fault analysis system, which includes an injection device, a simulation analysis device, and a nuclear power simulation platform based on the virtual DCS. The fault analysis method includes the following steps: The DCS fault data is sent to the injection device, wherein the DCS fault data includes the fault point, monitoring variables and simulation time; The injection device generates fault variables, control commands, and monitoring commands based on the fault point and the simulation time, sends the fault variables and control commands to the nuclear power simulation platform, and sends the monitoring variables and monitoring commands to the simulation analysis device; The nuclear power simulation platform performs simulation based on the fault variables and the control commands. The simulation analysis equipment monitors the simulation process of the nuclear power simulation platform based on the monitoring variables and the monitoring commands, and obtains the monitoring results corresponding to the monitoring variables.

[0006] Secondly, embodiments of the present invention provide a fault analysis system based on a virtual DCS, the fault analysis system comprising: Injection equipment, simulation analysis equipment, and a nuclear power simulation platform based on the virtual DCS; The injection device is used to acquire DCS fault data, wherein the DCS fault data includes fault point, monitoring variables and simulation time; based on the fault point and the simulation time, fault variables, control commands and monitoring commands are generated, the fault variables and the control commands are sent to the nuclear power simulation platform, and the monitoring variables and the monitoring commands are sent to the simulation analysis device; The nuclear power simulation platform is used to perform simulations based on the fault variables and the control commands. The simulation analysis equipment is used to monitor the simulation process of the nuclear power simulation platform according to the monitoring variables and the monitoring instructions, and to obtain the monitoring results corresponding to the monitoring variables.

[0007] The beneficial effects of this invention compared to existing technologies are as follows: The fault analysis method of this invention is applied to a fault analysis system, which includes an injection device, a nuclear power simulation platform based on a virtual DCS fault system, and a simulation analysis device. DCS fault data is sent to the injection device, wherein the DCS fault data includes fault points, monitoring variables, and simulation time. The injection device generates fault variables, control commands, and monitoring commands based on the fault points and simulation time, and sends the fault variables and control commands to the nuclear power simulation platform. The monitoring variables and monitoring commands are also sent to the simulation analysis device. The nuclear power simulation platform executes simulation based on the fault variables and control commands. The simulation analysis device monitors the simulation process of the nuclear power simulation platform based on the monitoring variables and monitoring commands, and obtains the monitoring results corresponding to the monitoring variables.

[0008] Among them, the fault analysis system, constructed by injection equipment, nuclear power simulation platform and simulation analysis equipment, automatically simulates and monitors the impact of various fault scenarios. When a fault occurs in the actual operation of the real DCS, it can more accurately locate the fault point that triggers the fault based on the actual fault performance and monitoring results, shorten the fault analysis and troubleshooting time, improve the efficiency of fault analysis in nuclear power plants and the accuracy of fault analysis results, and determine the scope of the fault's impact through monitoring results. Thus, effective measures can be taken in a timely and accurate manner according to the scope of the fault's impact to prevent the fault from worsening and ensure the safe operation of the nuclear power plant. Attached Figure Description

[0009] To more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings used in the description of the embodiments of the present invention will be briefly introduced below. Obviously, the drawings described below are only some embodiments of the present invention. For those skilled in the art, other drawings can be obtained based on these drawings without creative effort.

[0010] Figure 1 This is a schematic diagram of the structure of a fault analysis system based on a virtual DCS provided in Embodiment 1 of the present invention; Figure 2 This is a flowchart illustrating a fault analysis method based on a virtual DCS provided in Embodiment 2 of the present invention; Figure 3 This is a schematic diagram of the overall process of a fault analysis method based on a virtual DCS provided in Embodiment 2 of the present invention; Figure 4 This is a flowchart illustrating a fault analysis method based on a virtual DCS provided in Embodiment 3 of the present invention; Figure 5 This is a flowchart illustrating a fault analysis method based on a virtual DCS provided in Embodiment 4 of the present invention; Figure 6 This is a flowchart illustrating a fault analysis method based on a virtual DCS provided in Embodiment 5 of the present invention; Figure 7 This is a schematic diagram of DCS fault data provided in Embodiment 5 of the present invention; Figure 8 This is a flowchart illustrating a fault analysis method based on a virtual DCS provided in Embodiment Six of the present invention; Figure 9 This is a flowchart illustrating a fault analysis method based on a virtual DCS provided in Embodiment 7 of the present invention; Figure 10 This is a flowchart illustrating a fault analysis method based on a virtual DCS provided in Embodiment 8 of the present invention; Figure 11 This is a flowchart illustrating a fault analysis method based on a virtual DCS provided in Embodiment 9 of the present invention.

[0011] Among them, 100 is a fault analysis system based on virtual DCS, 110 is a hot-swappable interface, 120 is an injection device, 130 is a nuclear power simulation platform, 131 is a safety-grade virtual DCS, 132 is a non-safety-grade virtual DCS, 133 is a nuclear power plant process model, 140 is a simulation analysis device, and 150 is a visualization platform. Detailed Implementation

[0012] The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some, not all, of the embodiments of the present invention. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0013] like Figure 1The diagram shown is a structural schematic of a fault analysis system based on a virtual DCS provided in Embodiment 1 of the present invention. The fault analysis system includes: Injection device 120, simulation analysis device 140, and nuclear power simulation platform 130 based on virtual DCS; The injection device 120 is used to acquire DCS fault data, which includes fault point, monitoring variables and simulation time; based on the fault point and simulation time, fault variables, control commands and monitoring commands are generated, and the fault variables and control commands are sent to the nuclear power simulation platform 130, and the monitoring variables and monitoring commands are sent to the simulation analysis device 140. The nuclear power simulation platform 130 is used to perform simulations based on fault variables and control commands; The simulation analysis equipment 140 is used to monitor the simulation process of the nuclear power simulation platform 130 according to the monitoring variables and monitoring instructions, and to obtain the monitoring results corresponding to the monitoring variables.

[0014] In this embodiment, the injection device 120, the nuclear power simulation platform 130, and the simulation analysis device 140 are connected in communication. The injection device 120 is used to acquire DCS fault data, generate fault variables, control commands, and monitoring commands, send the fault variables and control commands to the nuclear power simulation platform 130, and send the monitoring variables and monitoring commands to the simulation analysis device 140. The injection device 120 can be used to acquire and store DCS fault data in batches, and automatically complete the injection and simulation control of DCS fault data in sequence, realizing the "unattended" function of the entire fault analysis process. The injection device 120 has query and filtering functions, and can acquire multiple versions of DCS fault data. During simulation, a portion of the DCS fault data can be selected and executed sequentially. When the nuclear power simulation platform 130 experiences a system crash, the injection device 120 is used to repair the nuclear power simulation platform 130 according to a preset fault handling program.

[0015] The nuclear power simulation platform 130 includes a virtual DCS system and a nuclear power plant process model 133. The nuclear power simulation platform 130 is used to perform simulations based on fault variables and control commands. The modeling data of the nuclear power plant process model 133 comes from actual nuclear power design data. Through multiple rounds of consistency upgrades, the nuclear power plant process model 133 has a high degree of consistency with the actual nuclear power plant.

[0016] The simulation analysis device 140 is used to monitor the simulation process of the nuclear power simulation platform 130 according to the monitoring variables and monitoring instructions, and obtain the monitoring results corresponding to the monitoring variables. The simulation analysis device 140 has a query function, which supports querying by stored fault name, fault type, alarm name and number of monitoring equipment, etc. The simulation analysis device 140 has an analysis function, which supports quantity statistics, curve reproduction and analysis of simulated quantities, comparative analysis of multiple variables in the same window, and flexible adjustment of curve variables, quantities, coordinates, etc.

[0017] Optionally, the virtual DCS includes a safety-level virtual DCS131 and a non-safety-level virtual DCS132. The safety-level virtual DCS132 performs simulation on safety-level fault variables, while the non-safety-level virtual DCS132 is used to perform simulation on non-safety-level fault variables.

[0018] Optionally, the fault analysis system 100 also includes a hot-swappable interface 110, which is used to connect a fault acquisition board to obtain the actual DCS board fault data collected by the fault acquisition board during actual operation; the hot-swappable interface 110 is used to generate DCS fault data based on the board fault data and send the DCS fault data to the injection device 120.

[0019] Optionally, the fault analysis system 100 also includes a visualization platform 150. The visualization platform 150 is used to associate, record, and display fault points, monitoring variables, and monitoring results. The visualization platform 150 has equipment fault analysis and statistics capabilities, allowing for flexible statistical analysis and classification according to dimensions such as equipment type, fault type, and time period (year, quarter, month). It implements conventional analysis tools such as charts and curves. It has the function of outputting analysis results in a specific format, such as outputting a PDF file. The visualization platform 150 also has an in-system early warning function. When a preset warning threshold is reached, the system automatically pushes equipment warning information: for example, if the same equipment experiences more than 4 faults within a month, an alarm is triggered. The alarm triggering conditions can be manually set.

[0020] In this embodiment, a fault analysis system constructed using injection equipment, a nuclear power simulation platform, and simulation analysis equipment automatically simulates and monitors various fault scenarios. This enables the system to more accurately locate the fault point that triggers the fault when a fault occurs in the actual operation of the real DCS, based on the actual fault performance and monitoring results. This shortens the time for fault analysis and troubleshooting, improves the efficiency and accuracy of fault analysis results in nuclear power plants, and determines the scope of the fault's impact through monitoring results. Based on the scope of the fault's impact, effective measures can be taken in a timely and accurate manner to prevent the fault from worsening and ensure the safe operation of the nuclear power plant.

[0021] like Figure 2The diagram shown is a flowchart of a fault analysis method based on a virtual DCS provided in Embodiment 2 of the present invention. This fault analysis method is applied to a fault analysis system, which includes an injection device, a simulation analysis device, and a nuclear power simulation platform built based on a virtual DCS. The fault analysis method includes the following steps: Step S201: Send the DCS fault data to the injection device, wherein the DCS fault data includes the fault point, monitoring variables and simulation time.

[0022] In this embodiment, DCS refers to Distributed Control System (DCS). Virtual DCS can refer to a virtual nuclear power plant DCS obtained by porting the software of a real nuclear power plant DCS to a simulator environment. The performance and physical fidelity of the virtual DCS are exactly the same as those of the real nuclear power plant DCS. Nuclear power simulation platform can refer to a virtual nuclear power simulation environment built based on virtual DCS. Inference and analysis equipment can refer to computer equipment that monitors and analyzes the simulation process of the nuclear power simulation platform. Injection equipment can refer to computer equipment that realizes dynamic identification and inference injection of simulation data.

[0023] DCS fault data refers to fault data of the distributed control system of a nuclear power plant. Fault point can refer to the variable name and corresponding value that need to be set to trigger the fault. Monitoring variable can refer to the variable that the simulation analysis equipment needs to monitor and record during the simulation process of the nuclear power simulation platform. Simulation time can refer to the time of simulation and simulation of DCS fault data.

[0024] Specifically, multiple DCS fault data can be acquired, and the acquired DCS fault data can be imported into the injection tool in batches. The injection tool accepts and stores the DCS fault data in batches. Alternatively, a single DCS fault or a combination of faults can be acquired, and the acquired DCS faults or combinations of faults can be imported into the injection tool. The injection tool accepts and stores the DCS faults or combinations of faults in batches.

[0025] Step S202: The injection device generates fault variables, control commands, and monitoring commands based on the fault point and simulation time, sends the fault variables and control commands to the nuclear power simulation platform, and sends the monitoring variables and monitoring commands to the simulation analysis device.

[0026] In this embodiment, the fault variable can refer to the variable that needs to be set to trigger a fault, the control command can refer to the command that controls the nuclear power simulation platform to perform simulation, and can include a start simulation command that indicates the start of the simulation and an end simulation command that indicates the end of the simulation, and the monitoring command can refer to the command that controls the simulation analysis equipment to perform monitoring analysis, and can include a start monitoring command that indicates the start of monitoring and an end monitoring command that indicates the end of monitoring. The start simulation command and the start monitoring command can be the same or different, and the end simulation command and the end monitoring command can be the same or different.

[0027] Specifically, the injection device dynamically identifies the acquired DCS fault data, extracts the fault point, monitoring variables, and simulation time, extracts the fault variables from the fault point, and generates start simulation command, end simulation command, start monitoring command, and end monitoring command based on the simulation time. The fault variables, start simulation command, and end simulation command are sent to the nuclear power simulation platform, and the monitoring variables, start monitoring command, and end monitoring command are sent to the simulation analysis device.

[0028] Optionally, DCS fault data can be directly sent to the nuclear power simulation platform. The nuclear power simulation platform generates fault variables, monitoring variables, control commands, and monitoring commands based on the acquired DCS fault data, and sends the monitoring variables and monitoring commands to the simulation analysis equipment.

[0029] Step S203: The nuclear power simulation platform executes the simulation based on the fault variables and control commands. The simulation analysis equipment monitors the simulation process of the nuclear power simulation platform based on the monitoring variables and monitoring commands, and obtains the monitoring results corresponding to the monitoring variables.

[0030] In this embodiment, the monitoring result can refer to the range of influence of the monitored variables obtained by the simulation analysis equipment monitoring the simulation process of the nuclear power simulation platform. For example, the monitoring result can be a trend curve, a sequence of key evolutionary events, and a list of parameters.

[0031] Specifically, the nuclear power simulation platform sets parameters for fault variables according to the start simulation command, triggers the start of simulation at the fault point, and the simulation analysis equipment starts monitoring and recording the parameter outputs of the monitored variables during the simulation process according to the start monitoring command. When the simulation time reaches the simulation time limit, the nuclear power simulation platform stops the simulation according to the end simulation command, and the simulation analysis equipment stops monitoring according to the end monitoring command.

[0032] like Figure 3The diagram shown illustrates the overall process of a fault analysis method based on a virtual DCS, as provided in Embodiment 2 of the present invention. The fault analysis system includes an injection device, a nuclear power simulation platform, and a simulation analysis device. Since the DCS fault data is in list format, the overall process for fault analysis of the DCS fault data can be as follows: 1) Import DCS fault list versions A, B, and C into the injection device in batches. The injection device receives the information in batches and stores the DCS fault list information. 2) Perform pre-simulation initialization. The injection device sends a start command to the nuclear power simulation platform and the simulation analysis device. The nuclear power simulation platform starts the nuclear power simulation program according to the start command, loads the virtual DCS and nuclear power simulation tasks, and the simulation analysis device starts the simulation analysis program according to the start command. 3) Perform fault simulation initialization. The injection device sends an initialization command to the nuclear power simulation platform and sends the monitoring variables to the simulation analysis device. The nuclear power simulation platform loads the initial operating conditions for the simulation according to the initialization command, and the simulation analysis device initializes the monitoring list according to the monitoring variables. 4) Start the simulation. The injection device sends a start simulation command to the nuclear power simulation platform and a start monitoring command to the simulation analysis device. The nuclear power simulation platform starts the simulation according to the start simulation command, and the simulation analysis device starts recording the parameter changes corresponding to the monitoring variables and listens for alarms for unmonitored variables according to the start monitoring command. 5) Stop the simulation. The injection device sends a termination simulation command to the nuclear power simulation platform and a termination simulation analysis device. The nuclear power simulation platform stops the simulation according to the termination simulation command, and the simulation analysis device stops monitoring according to the termination monitoring command and stores the monitoring results. 6) The injection device determines whether to execute the next DCS fault data. If it executes, it returns to the fault simulation initialization step. If it does not execute, it sends a shutdown command to the nuclear power simulation platform. The nuclear power simulation platform shuts down according to the shutdown command.

[0033] In this embodiment, a fault analysis system constructed using injection equipment, a nuclear power simulation platform, and simulation analysis equipment automatically simulates and monitors various fault scenarios. This enables the system to more accurately locate the fault point that triggers the fault when a fault occurs in the actual operation of the real DCS, based on the actual fault performance and monitoring results. This shortens the time for fault analysis and troubleshooting, improves the efficiency and accuracy of fault analysis results in nuclear power plants, and determines the scope of the fault's impact through monitoring results. Based on the scope of the fault's impact, effective measures can be taken in a timely and accurate manner to prevent the fault from worsening and ensure the safe operation of the nuclear power plant.

[0034] like Figure 4The diagram shown is a flowchart of a fault analysis method based on a virtual DCS provided in Embodiment 3 of the present invention. The virtual DCS includes a safety-level virtual DCS and a non-safety-level virtual DCS. The fault points include safety-level fault points and non-safety-level fault points. In step S202 above, the injection device generates fault variables, control commands, and monitoring commands based on the fault points and the estimated time, which may include the following steps: Step S401: The injection device generates safety-level fault variables, safety-level control commands, and monitoring commands based on the safety-level fault point and the estimated time.

[0035] Step S402: The injection device generates non-safety level fault variables, non-safety level control commands, and monitoring commands based on the non-safety level fault points and the estimated time.

[0036] In this embodiment, a safety-level fault point can refer to a fault that does not directly threaten the safety of the DCS. For example, the safety-level fault point may include redundancy function abnormality, network fault, and communication abnormality. The safety-level virtual DCS can refer to a virtual DCS that simulates the safety-level fault point. The safety-level fault variable can refer to the variable that needs to be set to trigger a safety-level fault. The safety-level control command can refer to the command that controls the safety-level virtual DCS to perform simulation.

[0037] Non-security-level fault points can refer to faults that directly threaten the security of the DCS. For example, non-security-level fault points can include faults of the computing server host / slave / dual machine, computing server network faults, and operator station network faults. Non-security-level virtual DCS can refer to a virtual DCS that simulates non-security-level fault points. Non-security-level fault variables can refer to variables that need to be set to trigger non-security-level faults. Non-security-level control commands can refer to commands that control the simulation of non-security-level virtual DCS.

[0038] Specifically, the injection device dynamically identifies the acquired DCS fault data, determines safety-level fault points, non-safety-level fault points, and simulation times, extracts safety-level fault variables from safety-level fault points, extracts non-safety-level fault variables from non-safety-level fault points, generates safety-level control commands and monitoring commands based on the simulation times corresponding to safety-level fault points, and generates non-safety-level control commands and monitoring commands based on the simulation times corresponding to non-safety-level fault points.

[0039] In step S203 above, the nuclear power simulation platform performs simulation based on fault variables and control commands, which may include the following steps: Step S403: The nuclear power simulation platform instructs the safety-level virtual DCS to perform simulation of safety-level fault variables according to the safety-level control instructions.

[0040] Step S404: The nuclear power simulation platform instructs the non-safety level virtual DCS to perform simulation of non-safety level fault variables according to the non-safety level control instructions.

[0041] Specifically, the nuclear power simulation platform, based on safety-level control commands, enables the safety-level virtual DCS to set parameters for safety-level fault variables, triggers simulation and deduction of the safety-level fault variables, and stops the simulation when the deduction time is reached. Correspondingly, the nuclear power simulation platform, based on non-safety-level control commands, enables the non-safety-level virtual DCS to set parameters for non-safety-level fault variables, triggers simulation and deduction of the non-safety-level fault variables, and stops the simulation when the deduction time is reached.

[0042] In this embodiment, by dividing the virtual DCS into safety-level virtual DCS and non-safety-level virtual DCS, and classifying fault points into safety-level fault points and non-safety-level fault points, the safety-level virtual DCS simulates safety-level fault points, and the non-safety-level virtual DCS simulates non-safety-level fault points. Each virtual DCS can focus on a specific type of fault point, thereby enabling more in-depth simulation and deduction of related fault scenarios, improving the accuracy of simulation results, optimizing simulation resource allocation, improving simulation efficiency, and reducing the safety risks introduced by simulating non-safety-level fault points, thus ensuring the overall safety and stability of the nuclear power simulation platform.

[0043] like Figure 5 The diagram shown is a flowchart of a fault analysis method based on a virtual DCS provided in Embodiment 4 of the present invention. After sending the DCS fault data to the injection device in step S201 above, the following steps may also be included: Step S501: The injection device sends a start command to the nuclear power simulation platform and the simulation analysis equipment.

[0044] Step S502: The nuclear power simulation platform starts the nuclear power simulation program according to the start command, and loads the safety-level virtual DCS, non-safety-level virtual DCS and nuclear power simulation tasks.

[0045] Step S503: The simulation analysis equipment starts the simulation analysis program according to the start command.

[0046] In this embodiment, the start command can refer to the command to start the nuclear power simulation platform and the simulation analysis equipment, the nuclear power simulation program can refer to the code that simulates the fault, the nuclear power simulation task can refer to the task that simulates the fault, and the simulation analysis program can refer to the code that monitors the simulation process.

[0047] Specifically, the injection device sends a start command to the nuclear power simulation platform and the simulation analysis device. The nuclear power simulation platform starts the nuclear power simulation program according to the start command, loads the safety-level virtual DCS, the non-safety-level virtual DCS and the nuclear power simulation task, and the simulation analysis device starts the simulation analysis program according to the start command.

[0048] In this embodiment, the nuclear power simulation platform and simulation analysis equipment are started through a unified startup command and program loading process, which simplifies the startup process.

[0049] like Figure 6 The diagram shown is a flowchart of a fault analysis method based on a virtual DCS provided in Embodiment 5 of the present invention. The DCS fault data also includes a safety-level initial operating condition identifier and a non-safety-level initial operating condition identifier. After sending the DCS fault data to the injection device in step S201 above, the following steps may also be included: Step S601: The injection device generates a safety-level initialization command based on the safety-level initial operating condition identifier, and generates a non-safety-level initialization command based on the non-safety-level initial operating condition identifier.

[0050] In step S502 above, after the nuclear power simulation platform starts the nuclear power simulation program according to the start command and loads the safety-level virtual DCS, non-safety-level virtual DCS, and nuclear power simulation tasks, it may also include the following steps: Step S602: The injection device sends safety-level initialization instructions and non-safety-level initialization instructions to the nuclear power simulation platform.

[0051] In this embodiment, the virtual DCS can simulate faults under various nuclear power conditions, including normal startup, shutdown, normal operation transients, and accident transients. The initial operating condition refers to the initial state in which the virtual DCS performs fault simulation. This initial operating condition can be preset in the database of the nuclear power simulation platform. The initial operating condition identifier can be a number that identifies the initial operating condition. For example, the initial operating condition can include 1) RP mode, nuclear power 10%Pn; 2) NS / SG mode, standard hot shutdown, APD water supply; 3) NS / RRA mode, cold shutdown, etc. The safety-level initialization instruction can be an instruction that instructs the safety-level virtual DCS to load a specific initial operating condition for initialization, and the non-safety-level initialization instruction can be an instruction that instructs the non-safety-level virtual DCS to load a specific initial operating condition for initialization.

[0052] Specifically, the injection device generates a safety-level initialization command based on the safety-level initial operating condition identifier and a non-safety-level initialization command based on the non-safety-level initial operating condition identifier. After the nuclear power simulation platform starts according to the start command, the safety-level initialization command and the non-safety-level initialization command are sent to the nuclear power simulation platform.

[0053] Before the nuclear power simulation platform performs the simulation based on the fault variables and control commands in step S203 above, the following steps may also be included: Step S603: The nuclear power simulation platform, according to the safety level initialization command, instructs the safety level virtual DCS to load the initial operating conditions for simulating safety level fault variables.

[0054] Step S604: The nuclear power simulation platform instructs the non-safety level virtual DCS to load the initial operating conditions for simulating non-safety level fault variables according to the non-safety level initialization command.

[0055] Specifically, after receiving a safety-level initialization command, the nuclear power simulation platform loads specific initial operating conditions from the nuclear power simulation platform's database to perform operating condition initialization. After receiving a non-safety-level initialization command, the non-safety-level virtual DCS loads specific initial operating conditions from the nuclear power simulation platform's database to perform operating condition initialization.

[0056] For example, such as Figure 7 The diagram shown is a schematic representation of DCS fault data provided in Embodiment 5 of the present invention. The DCS fault data is in list format and includes a serial number, fault number, fault name, fault point, initial state identifier, monitoring variables, and simulation time.

[0057] The serial number is used to identify each row of DCS fault data in the list. The fault number includes information such as unit, safety level, system name, fault type and subtype. The fault name is used to indicate the name of the fault being simulated. The fault point can refer to the fault variable and corresponding value that need to be set to trigger the fault in the virtual DCS. The initial state identifier can be used to indicate the initial state that the virtual DCS needs to load before performing simulation on the fault variable. The monitoring variable can refer to the variable that the simulation analysis equipment needs to monitor and record during the simulation process. This batch of variables can be monitored by calling curves. The simulation time can refer to the time when the corresponding fault point is simulated and the monitoring results are recorded in the fault analysis system. This time can be set and adjusted manually as needed.

[0058] For DCS fault data with serial number 1001, its fault number is 5-1E-RPCI-A-1, indicating Unit 5 safety-level RPCI network fault 1, and its fault name is Unit 5 safety-level RPCI network fault. Based on its fault point, it is determined that to trigger the fault, the fault variables mfGRE01.CurrValue and rfGSE07.CurrValue need to be set to 1, and the fault variable tr_GRE0362MM.Input needs to be set to 0.5. Based on its initial state identifier 101, it is determined that before performing simulation on this fault point, the initial state corresponding to number 101 needs to be loaded from the nuclear power simulation platform data. Regarding its monitoring variables, it is determined that during the simulation of this fault point, the variables that the simulation analysis equipment needs to record are tr_VVP002MD.Output, tr_VVP003MD.Output, tr_VVP001MD.Output, and tr_VVP004MD.Output. Regarding its simulation time, it is determined that the simulation simulation time is 600 seconds.

[0059] In this embodiment, the DCS fault data also includes safety-level initial condition identifiers and non-safety-level initial condition identifiers. Before executing the simulation, specific initial conditions for simulating fault variables are loaded according to safety-level initialization instructions and non-safety-level initialization instructions. By loading specific initial conditions before simulation, the virtual DCS can more accurately simulate the impact and changes of faults in a real DCS, improving the accuracy and reliability of the simulation results. Furthermore, by setting different initial conditions, the impact range of faults in different scenarios can be comprehensively simulated, improving the comprehensiveness of the simulation results.

[0060] like Figure 8 The diagram shown is a flowchart of a fault analysis method based on a virtual DCS provided in Embodiment Six of the present invention. The fault analysis system also includes a hot-swappable interface for connecting a fault acquisition board. The fault acquisition board is used to collect board fault data of the real DCS during actual operation. Before sending the DCS fault data to the injection device in step S201 above, the following steps may also be included: Step S801: The hot-swappable interface acquires the board fault data collected by the fault acquisition board, and generates DCS fault data based on the board fault data.

[0061] Sending DCS fault data to the injection device in step S201 above may include the following steps: Step S802: The hot-swappable interface sends DCS fault data to the injection device.

[0062] In this embodiment, the hot-swappable interface can refer to an interface that allows for immediate connection and removal of the device without shutting down the power or interrupting the system operation. The hot-swappable interface is used to connect the fault acquisition board, which is used to collect board fault data of the actual DCS during actual operation.

[0063] Specifically, the fault acquisition board collects board fault data during the actual operation of the DCS. When performing fault analysis, the board fault data is obtained from the fault acquisition board through a hot-swappable interface. The obtained board fault data is then processed to obtain DCS fault data, which is then sent to the injection device through the hot-swappable interface.

[0064] In this embodiment, the fault analysis system also includes a hot-swappable interface for connecting a fault acquisition board. This board collects board fault data from the actual DCS during operation. The hot-swappable interface's ability to instantly connect and disconnect devices facilitates the acquisition of board fault data and DCS fault data. Based on the board fault data collected by the fault acquisition board, DCS fault data is obtained, enabling the virtual DCS to simulate actual fault conditions. This makes the fault simulation analysis more realistic and improves the accuracy of the simulation analysis. Furthermore, the simulation results based on this DCS fault data can directly resolve faults in the real DCS, enhancing the effectiveness of the simulation analysis results for the real DCS.

[0065] like Figure 9 The diagram shown is a flowchart of a fault analysis method based on a virtual DCS provided in Embodiment 7 of the present invention. The fault analysis system also includes a visualization platform. After sending the DCS fault data to the injection device in step S201 above, the following steps may also be included: Step S901: The injection device sends the fault point and monitoring variables to the visualization platform.

[0066] After obtaining the monitoring results corresponding to the monitored variables in step S203 above, the following steps may also be included: Step S902: The simulation and analysis equipment sends the monitoring results to the visualization platform.

[0067] Step S903: The visualization platform associates, records, and displays the fault point, monitoring variables, and monitoring results.

[0068] In this embodiment, the visualization platform can refer to a platform that includes a graphical interface and interactive operation.

[0069] Specifically, after the DCS fault data is sent to the injection device, the fault point and monitoring variables of the injection device are sent to the visualization platform. After the simulation analysis device obtains the monitoring results corresponding to the monitoring variables, the simulation analysis device sends the monitoring results to the visualization platform. The visualization platform associates, records and displays the fault point, monitoring variables and monitoring results.

[0070] In this embodiment, the fault analysis system also includes a visualization platform. After the simulation analysis equipment obtains the monitoring results, the visualization platform associates, records, and displays the monitoring results, monitoring variables, and corresponding fault points. This allows users to intuitively see the monitoring results and corresponding fault points. When a fault occurs in the actual operation of the real DCS, the monitoring results displayed on the visualization platform can be compared with the actual fault manifestations to more accurately locate the fault point that triggered the fault, shortening the time for fault analysis and troubleshooting, and improving the efficiency and accuracy of fault analysis results in nuclear power plants.

[0071] like Figure 10 The diagram shown is a flowchart of a fault analysis method based on a virtual DCS provided in Embodiment 8 of the present invention. After obtaining the monitoring results corresponding to the monitored variables in step S203 above, the following steps may also be included: Step S1001: Send the DCS fault guideline data to the simulation and analysis equipment.

[0072] Step S1002: The simulation and analysis equipment generates the control strategy corresponding to the monitoring results based on the DCS fault guideline data and monitoring results.

[0073] In this embodiment, DCS fault guidance data can refer to guidance methods for handling DCS faults. For example, the DCS fault guidance data may include fault handling methods, emergency plans, and the importance of components.

[0074] Specifically, after the simulation and analysis equipment obtains the monitoring results, it sends the DCS fault guideline data to the simulation and analysis equipment. The simulation and analysis equipment then generates the corresponding control strategy based on the fault handling methods and monitoring results recorded in the DCS fault guideline data.

[0075] Optionally, after generating the control strategy, the simulation and analysis equipment can send the control strategy to the visualization platform in a preset standard format. The visualization platform will record and display the fault point, monitoring variables, monitoring results and corresponding control strategies.

[0076] In this embodiment, after obtaining the monitoring results, the simulation analysis device generates a corresponding control strategy based on the monitoring results and DCS fault guideline data. This enables the real DCS to respond to faults in real operation based on the fault strategy, thereby improving the efficiency of fault handling.

[0077] like Figure 11 The diagram shown is a flowchart of a fault analysis method based on a virtual DCS provided in Embodiment 9 of the present invention. After the nuclear power simulation platform performs simulation based on fault variables and control commands in step S203 above, the following steps may also be included: Step S1101: For non-monitored variables not included in the DCS fault data, the simulation analysis equipment monitors the simulation process of the nuclear power simulation platform based on the non-monitored variables.

[0078] Step S1102: When the monitored variable meets the alarm condition, the non-monitored variable is marked.

[0079] In this embodiment, non-monitored variables can refer to variables not listed in the DCS fault data.

[0080] Specifically, for non-monitored variables not listed in the DCS fault data, the simulation analysis equipment listens to all of them. When a non-monitored variable triggers an alarm, the name of the non-monitored variable and the trigger time are recorded. When the alarm disappears, the time of disappearance is recorded. For non-monitored variables that repeatedly trigger and clear alarms, the time of each action is recorded. At the same time, for digital quantities, all variables from 0 to 1 or from 1 to 0 are recorded and stored.

[0081] In this embodiment, by monitoring non-monitored variables and marking them when alarm conditions are met, the simulation analysis equipment can capture overlooked faults that, even when abnormal, can still affect system stability, thus providing timely early warning and ensuring the safe operation of the nuclear power plant.

[0082] The implementation of all or part of the processes in the methods of the above embodiments can also be accomplished by a computer program product. When the computer program product is run on a computer device, it enables the computer device to execute the steps in the above method embodiments.

[0083] In the above embodiments, the descriptions of each embodiment have different focuses. For parts that are not described in detail or recorded in a certain embodiment, please refer to the relevant descriptions of other embodiments.

[0084] Those skilled in the art will recognize that the units and algorithm steps of the various examples described in conjunction with the embodiments disclosed herein can be implemented in electronic hardware, or a combination of computer software and electronic hardware. Whether these functions are implemented in hardware or software depends on the specific application and design constraints of the technical solution. Those skilled in the art can use different methods to implement the described functions for each specific application, but such implementation should not be considered beyond the scope of this application.

[0085] In the embodiments provided in this application, it should be understood that the disclosed apparatus / computer devices and methods can be implemented in other ways. For example, the apparatus / computer device embodiments described above are merely illustrative. For instance, the division of modules or units is only a logical functional division, and in actual implementation, there may be other division methods. For example, multiple units or components may be combined or integrated into another system, or some features may be ignored or not executed. Furthermore, the mutual coupling or direct coupling or communication connection shown or discussed may be through some interfaces; the indirect coupling or communication connection between apparatuses or units may be electrical, mechanical, or other forms.

[0086] The units described as separate components may or may not be physically separate. The components shown as units may or may not be physical units; that is, they may be located in one place or distributed across multiple network units. Some or all of the units can be selected to achieve the purpose of this embodiment according to actual needs.

[0087] The above embodiments are only used to illustrate the technical solutions of this application, and are not intended to limit them. Although this application has been described in detail with reference to the foregoing embodiments, those skilled in the art should understand that modifications can still be made to the technical solutions described in the foregoing embodiments, or equivalent substitutions can be made to some of the technical features. Such modifications or substitutions do not cause the essence of the corresponding technical solutions to deviate from the spirit and scope of the technical solutions of the embodiments of this application, and should all be included within the protection scope of this application.

Claims

1. A fault analysis method based on virtual DCS, characterized in that, The fault analysis method is applied to a fault analysis system, which includes an injection device, a simulation analysis device, and a nuclear power simulation platform built based on a virtual DCS. The fault analysis method includes the following steps: The DCS fault data is sent to the injection device, wherein the DCS fault data includes the fault point, monitoring variables and simulation time; The injection device generates fault variables, control commands, and monitoring commands based on the fault point and the simulation time, sends the fault variables and control commands to the nuclear power simulation platform, and sends the monitoring variables and monitoring commands to the simulation analysis device; The nuclear power simulation platform performs simulation based on the fault variables and the control commands. The simulation analysis equipment monitors the simulation process of the nuclear power simulation platform based on the monitoring variables and the monitoring commands, and obtains the monitoring results corresponding to the monitoring variables.

2. The fault analysis method based on virtual DCS as described in claim 1, characterized in that, The virtual DCS includes a security-level virtual DCS and a non-security-level virtual DCS. The fault points include both security-level and non-security-level fault points. The injection device generates fault variables, control commands, and monitoring commands based on the fault points and the simulation time, including: The injection device generates a safety-level fault variable, a safety-level control command, and a monitoring command based on the safety-level fault point and the simulation time. The injection device generates non-safety level fault variables, non-safety level control commands, and monitoring commands based on the non-safety level fault points and the simulation time. The nuclear power simulation platform performs simulations based on the fault variables and the control commands, including: The nuclear power simulation platform instructs the safety-level virtual DCS to perform simulation of the safety-level fault variables according to the safety-level control instructions. The nuclear power simulation platform instructs the non-safety level virtual DCS to perform simulation of the non-safety level fault variables according to the non-safety level control command.

3. The fault analysis method based on virtual DCS as described in claim 2, characterized in that, After sending the DCS fault data to the injection device, the method further includes: The injection device sends a start command to the nuclear power simulation platform and the simulation analysis device; The nuclear power simulation platform starts the nuclear power simulation program according to the start command, and loads the safety-level virtual DCS, non-safety-level virtual DCS and nuclear power simulation tasks; The simulation analysis device starts the simulation analysis program according to the start command.

4. The fault analysis method based on virtual DCS as described in claim 3, characterized in that, The DCS fault data also includes a safety-level initial operating condition identifier and a non-safety-level initial operating condition identifier. After sending the DCS fault data to the injection device, it further includes: The injection device generates a safety-level initialization command based on the safety-level initial operating condition identifier, and generates a non-safety-level initialization command based on the non-safety-level initial operating condition identifier. After the nuclear power simulation platform starts the nuclear power simulation program according to the start command, and loads the safety-level virtual DCS, non-safety-level virtual DCS, and nuclear power simulation task, it further includes: The injection device sends the safety-level initialization command and the non-safety-level initialization command to the nuclear power simulation platform; Before the nuclear power simulation platform performs the simulation based on the fault variables and the control commands, it further includes: The nuclear power simulation platform, according to the safety level initialization command, instructs the safety level virtual DCS to load the initial operating conditions for simulating the safety level fault variables; The nuclear power simulation platform, according to the non-safety level initialization command, instructs the non-safety level virtual DCS to load the initial operating conditions for simulating the non-safety level fault variables.

5. The fault analysis method based on virtual DCS as described in claim 1, characterized in that, The fault analysis system also includes a hot-swappable interface for connecting a fault acquisition board. This fault acquisition board is used to collect board fault data from a real DCS during actual operation. Before sending the DCS fault data to the injection device, the system further includes: The hot-swappable interface acquires the board fault data collected by the fault acquisition board, and generates the DCS fault data based on the board fault data. Sending DCS fault data to the injection device includes: The hot-swappable interface sends the DCS fault data to the injection device.

6. The fault analysis method based on virtual DCS as described in claim 1, characterized in that, The fault analysis system also includes a visualization platform, and after sending the DCS fault data to the injection device, it further includes: The injection device sends the fault point and the monitoring variables to the visualization platform; After obtaining the monitoring results corresponding to the monitored variables, the process further includes: The simulation and analysis equipment sends the monitoring results to the visualization platform; The visualization platform associates, records, and displays the fault point, the monitoring variable, and the monitoring result.

7. The fault analysis method based on virtual DCS as described in claim 1, characterized in that, After obtaining the monitoring results corresponding to the monitored variables, the process further includes: Send the DCS fault guidance data to the simulation and analysis device; The simulation and analysis equipment generates a control strategy corresponding to the monitoring results based on the DCS fault guideline data and the monitoring results.

8. The fault analysis method based on virtual DCS as described in claim 1, characterized in that, After the nuclear power simulation platform performs the simulation based on the fault variables and the control commands, it further includes: For non-monitored variables not included in the DCS fault data, the simulation analysis equipment monitors the simulation process of the nuclear power simulation platform based on the non-monitored variables; When the monitored variable meets the alarm condition, the non-monitored variable is marked.

9. The fault analysis method based on virtual DCS as described in claim 1, characterized in that, The fault analysis method also includes: When the nuclear power simulation platform malfunctions, the injection device repairs the nuclear power simulation platform according to a preset fault handling procedure.

10. A fault analysis system based on a virtual DCS, characterized in that, The fault analysis system includes: Injection equipment, simulation analysis equipment, and a nuclear power simulation platform based on the virtual DCS; The injection device is used to acquire DCS fault data, wherein the DCS fault data includes fault point, monitoring variables and simulation time; based on the fault point and the simulation time, fault variables, control commands and monitoring commands are generated, the fault variables and the control commands are sent to the nuclear power simulation platform, and the monitoring variables and the monitoring commands are sent to the simulation analysis device; The nuclear power simulation platform is used to perform simulations based on the fault variables and the control commands. The simulation analysis equipment is used to monitor the simulation process of the nuclear power simulation platform according to the monitoring variables and the monitoring instructions, and to obtain the monitoring results corresponding to the monitoring variables.