Nuclear power station accident emergency command method and device
By obtaining real-time key safety parameters of nuclear power plants and using decision trees for accident diagnosis and emergency command, the problems of response delays and decision-making errors caused by manual judgment in traditional methods are solved, and rapid and accurate emergency response and decision support are achieved, thereby improving the safety management capabilities of nuclear power plants.
Patent Information
- Application Number
- CN202510914958.X
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2025-07-03
- Publication Date
- 2025-10-17
AI Technical Summary
Traditional nuclear power plant accident emergency command methods rely on manual judgment and decision-making, lack flexibility and adaptability, and find it difficult to quickly adjust response strategies in extreme situations, resulting in delayed responses or incorrect decisions.
By obtaining real-time key safety parameters of nuclear power plants, using decision trees to diagnose accidents, generating alarm information, and predicting the development outcomes of various accidents, generating response plans, and integrating communication systems for information transmission and resource deployment.
It realizes automatic analysis of accident situations, generates alarm information and provides decision support, improves the speed and accuracy of nuclear power plant emergency response, and enhances the level of safety management.
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Figure CN120809315A_ABST
Abstract
Description
TECHNICAL FIELD
[0001] The present application relates to the technical field of nuclear power plant accident emergency handling, and in particular to a nuclear power plant accident emergency command method and device. BACKGROUND
[0002] In the widespread application of nuclear power energy, the safe operation of nuclear power plants is of great importance. Although modern nuclear power plants are designed with multiple safety measures, nuclear accidents in extreme conditions can still occur, as shown in the Fukushima nuclear accident. Once a nuclear accident occurs, how to quickly and effectively respond and command in order to minimize the impact on the environment and human health is a problem that needs to be solved.
[0003] Traditional nuclear power plant accident emergency command methods usually rely on manual judgment and decision-making, which may lead to delayed response or decision-making errors in high-pressure and complex accident environments. In addition, existing emergency command systems often lack sufficient flexibility and adaptability, making it difficult to quickly adjust response strategies for different types of accidents. SUMMARY
[0004] The present application aims to at least partially solve one of the technical problems in the related art.
[0005] To this end, the first object of the present application is to provide a nuclear power plant accident emergency command method to automatically analyze accident conditions, generate alarm information, and provide decision support.
[0006] The second object of the present application is to provide a nuclear power plant accident emergency command device.
[0007] The third object of the present application is to provide an electronic device.
[0008] The fourth object of the present application is to provide a computer-readable storage medium.
[0009] The fifth object of the present application is to provide a computer program product.
[0010] To achieve the above objects, the first aspect of the present application provides a nuclear power plant accident emergency command method, comprising:
[0011] acquiring real-time key safety parameters of a nuclear power plant;
[0012] when the key safety parameters exceed the safety threshold range, acquiring nuclear power plant operation data for accident diagnosis to obtain an accident diagnosis result; the accident diagnosis result includes a predicted accident type, an accident severity, and a response measure;
[0013] generating an alarm information according to the accident diagnosis result, and sending the alarm information according to an alarm information sending rule;
[0014] According to the accident diagnosis result, a plurality of predicted accident development results of accident development are predicted, and a plurality of coping schemes are generated according to the plurality of predicted accident development results.
[0015] To achieve the above object, the second aspect of the present application proposes a nuclear power plant accident emergency command device, comprising:
[0016] A data acquisition module is configured to acquire real-time key safety parameters of the nuclear power plant.
[0017] An accident diagnosis module is configured to acquire operation data of the nuclear power plant to perform accident diagnosis when the key safety parameters exceed the safety threshold range, to obtain an accident diagnosis result; the accident diagnosis result includes a predicted accident type, an accident severity, and a coping measure.
[0018] An accident alarm module is configured to generate alarm information according to the accident diagnosis result, and to send the alarm information according to an alarm information sending rule.
[0019] A strategy generation module is configured to predict a plurality of predicted accident development results of accident development according to the accident diagnosis result, and to generate a plurality of coping schemes according to the plurality of predicted accident development results.
[0020] To achieve the above object, the third aspect of the present application proposes an electronic device, comprising a processor and a memory in communication connection with the processor; the memory stores computer execution instructions; the processor executes the computer execution instructions stored in the memory to implement the method of the first aspect.
[0021] To achieve the above object, the fourth aspect of the present application proposes a computer readable storage medium, wherein the computer readable storage medium stores computer execution instructions; the computer execution instructions are executed by the processor to implement the method of the first aspect.
[0022] To achieve the above object, the fifth aspect of the present application proposes a computer program product, comprising a computer program; the computer program is executed by the processor to implement the method of the first aspect.
[0023] The nuclear power plant accident emergency command method and device provided by the application can automatically analyze the accident situation, generate alarm information, and provide decision support, which is of great significance for improving the safety management level of the nuclear power plant and the ability to respond to sudden accidents.
[0024] Additional aspects and advantages of the application will be described in the following description, will become apparent from the following description, or will be learned by practice of the application. BRIEF DESCRIPTION OF DRAWINGS
[0025] The above and / or additional aspects and advantages of the application will become apparent and be readily understood by reference to the following description, and by practicing the application, in conjunction with the accompanying drawings, in which:
[0026] Figure 1 A flowchart of a nuclear power plant accident emergency command method provided by an embodiment of the application;
[0027] Figure 2 A flowchart of a nuclear power plant accident emergency command method provided by another embodiment of the application;
[0028] Figure 3 A block diagram of a nuclear power plant accident emergency command device provided by an embodiment of the application;
[0029] Figure 4 A block diagram of an electronic device provided by an embodiment of the application. DETAILED DESCRIPTION
[0030] The embodiments of the application are described in detail below, examples of which are shown in the accompanying drawings, in which the same or similar reference signs represent the same or similar elements or elements having the same or similar functions throughout. The embodiments described below are exemplary and are intended to explain the application, and cannot be understood as limiting the application.
[0031] The nuclear power plant accident emergency command method, device and equipment of the embodiments of the application are described below with reference to the accompanying drawings.
[0032] Figure 1 A flowchart of a nuclear power plant accident emergency command method provided by an embodiment of the application;
[0033] It should be noted that the execution subject of the nuclear power plant accident emergency command method in the embodiments of the present application is a nuclear power plant accident emergency command device in the embodiments of the present application. The nuclear power plant accident emergency command device can be configured in an electronic device, so that the electronic device can perform a nuclear power plant accident emergency command function.
[0034] As shown in Figure 1 The nuclear power plant accident emergency command method includes the following steps:
[0035] In step S101, real-time key safety parameters of the nuclear power plant are obtained.
[0036] In some embodiments, the key safety parameters include, but are not limited to, reactor temperature, pressure in the reactor, radiation level, and cooling system state.
[0037] In some embodiments, the key safety parameters include temperature data of the reactor core and surrounding area, pressure data in the reactor, radiation dose rate at multiple key positions of the nuclear power plant, and multiple index data of the cooling system, wherein the multiple index data of the cooling system include flow rate, temperature, and pressure of the coolant. The temperature data is collected by multiple temperature collection devices deployed in the reactor core and surrounding area; the pressure data is obtained by periodically detecting the pressure in the reactor by a pressure sensor; the radiation dose rate is collected by multiple radiation detectors respectively deployed at multiple key positions of the nuclear power plant; and the multiple index data of the cooling system are collected by a flow meter, a temperature sensor, and a pressure sensor respectively deployed on the cooling system.
[0038] As an implementation, the temperature data of the reactor core and surrounding area is collected by multiple temperature collection devices deployed in the reactor core and surrounding area, which can be thermocouples or thermistor temperature sensors, etc. The temperature of multiple positions of the reactor is monitored by the multiple temperature collection devices, and the expression is T=f(t), where T is the temperature, t is the time, and the function f represents the curve of the temperature change with time.
[0039] As an implementation, the pressure in the reactor is periodically detected by a pressure sensor to collect the pressure data in the reactor to ensure that it is within a safe range. The expression of the pressure is P=p0+Δp, where P is the current pressure, p0 is the initial pressure, and Δp is the pressure change.
[0040] As an implementation, the radiation dose rate at each key position of the nuclear power plant is monitored by a radiation detector, and the expression of the radiation dose rate is R=R0e-λt, where R is the radiation dose rate, R0 is the initial dose rate, λ is the attenuation constant, and t is the time.
[0041] As an implementation, the flow rate, temperature and pressure of the coolant are monitored by the flow meter, temperature sensor and pressure sensor deployed on the cooling system to ensure the effectiveness of the cooling system, and the expression is Q=vAΔT, wherein Q is the heat transfer, v is the flow rate of the coolant, A is the flow area, and ΔT is the temperature difference.
[0042] In step S102, when the key safety parameter exceeds the safety threshold range, the nuclear power plant operation data is acquired for accident diagnosis to obtain an accident diagnosis result; the accident diagnosis result includes a predicted accident type, an accident severity and a response measure.
[0043] In some embodiments, when any one of the key safety parameters exceeds the safety threshold range of the parameter, an emergency response protocol is automatically started, that is, the monitored nuclear power plant operation data is quickly analyzed by the accident diagnosis system to obtain an accident diagnosis result, whether a real safety threat exists is confirmed according to the accident diagnosis result, and the possibility of false alarm is excluded by comparing with the data of other monitoring systems.
[0044] In some embodiments, when the key safety parameter exceeds the safety threshold range, the nuclear power plant operation data is acquired for accident diagnosis to obtain an accident diagnosis result; including:
[0045] When the key safety parameter exceeds the safety threshold range, the nuclear power plant operation data is acquired;
[0046] The nuclear power plant operation data is input into the trained decision tree, and the accident prediction and evaluation are performed according to the branch rules of the decision tree to obtain a predicted accident type, an accident severity and a response measure.
[0047] In this embodiment, the real-time nuclear power plant operation data is input into the decision tree, and the accident prediction and evaluation are performed according to the branch rules of the decision tree to output a predicted accident type, an accident severity and a response measure.
[0048] The construction method of the decision tree includes: acquiring a training data set, the training data set including historical operation data, sensor data and accident record data of the nuclear power plant, cleaning, normalizing and discretizing the data set in the training data set to obtain a sample data set; constructing a decision tree according to the sample data set; and recursively dividing the data set according to the selection branching standard of the feature until the stop condition is met; and using a cross-validation method to evaluate the performance of the decision tree to ensure its generalization ability.
[0049] As an example, the accident diagnosis system comprises a monitoring device, a data transmission module and a data processing unit, wherein the monitoring device comprises sensors deployed inside and outside the nuclear power plant for collecting nuclear power plant operation data required for accident diagnosis, providing a data source for the accident diagnosis system; the data transmission module is used to transmit the data collected by the monitoring device to the data processing unit; the data processing unit is used to process the received data; the data processing unit mainly simulates and evaluates the accident in real time through mathematical models.
[0050] In some embodiments, in the prediction and evaluation of the accident, before the nuclear power plant operation data is input into the trained decision tree, the following steps are included: the uncertainty or confusion degree of the data in the nuclear power plant operation data is measured by using the calculation of information entropy and conditional entropy.
[0051] The information entropy expression is:
[0052]
[0053] Wherein, D is a data set, and pi is the proportion of the i-th class sample in the data set D.
[0054] The expression of conditional entropy is:
[0055]
[0056] Wherein, Dv is a subset of attribute a taking a specific value v in data set D, and V is a set of all possible values of attribute a.
[0057] Step S103, according to the accident diagnosis result, generate alarm information, and send alarm information according to the alarm information sending rule.
[0058] Send alarm information to all relevant personnel through the integrated communication system, and instruct them to act according to the predetermined emergency procedure;
[0059] As an implementation manner, a detailed alarm information emergency notification plan is prepared in advance, including determining an emergency contact list, a communication process, an alarm information content template and a backup communication means, ensuring that the integrated communication system is in good condition, and regularly testing and maintaining; when the accident diagnosis system detects an emergency, immediately start the emergency response process, the relevant person in charge verifies the authenticity of the emergency, and authorizes the sending of the alarm; generate alarm information according to the alarm information content template, activate the integrated communication system, ensure that all communication channels are ready, send alarm information to all relevant personnel through the predetermined communication channel, and the alarm information includes a brief description of the emergency, the location, the recommended action plan and the emergency contact information; continuously monitor the development of the emergency, and be ready to update the alarm information and guidance at any time, and according to the change of the situation, send the updated alarm and guidance information to the relevant personnel through the integrated communication system.
[0060] Step S104, according to the accident diagnosis result, predicting multiple prediction accident development results of the accident development; and generating multiple response schemes according to the multiple prediction accident development results.
[0061] As an implementation manner, the decision support system is used to analyze the accident situation according to the accident diagnosis result, to predict the spread and influence of the accident by simulating various possible scenarios of the accident development, to obtain multiple prediction accident development results; according to the multiple prediction accident development results, multiple response schemes are obtained, each response scheme including resource allocation suggestions and personnel deployment strategies; the advantages and disadvantages of each response scheme can also be evaluated, and the most suitable response scheme can be selected; for example, according to the cost, efficiency and safety, the available resources including personnel, equipment, materials are evaluated, and the state and location of the resources are determined.
[0062] Therefore, according to the response scheme given by the decision support system, the deployment of emergency personnel and equipment can be dynamically adjusted to maximize the effect of accident control; the development of the accident and the state of the resources can also be monitored in real time, so as to timely adjust the response scheme, dynamically adjust the deployment of emergency personnel and equipment according to real-time data and the suggestion of the decision support system.
[0063] The scheme integrates the latest sensor technology, data analysis algorithm, and artificial intelligence decision support function, to ensure that rapid and accurate emergency response can be realized when an accident occurs; the scheme can also dynamically adjust the response scheme according to the development of the accident.
[0064] The nuclear power plant accident emergency command method and device provided by the present application can obtain real-time key safety parameters of the nuclear power plant; when the key safety parameters exceed the safety threshold range, the operation data of the nuclear power plant is obtained for accident diagnosis to obtain an accident diagnosis result; an alarm information is generated according to the accident diagnosis result; and multiple prediction accident development results of the accident development are predicted according to the accident diagnosis result; and multiple response schemes are generated according to the multiple prediction accident development results; the scheme can automatically analyze the accident situation, generate alarm information and provide decision support, which is of great significance for improving the safety management level of the nuclear power plant and the ability to respond to sudden accidents.
[0065] On the basis of any of the above embodiments, the scheme further includes the following steps after step S104, as shown in Figure 2
[0066] Step S105, according to the response scheme, implementing isolation measures; and adjusting the isolation measures in real time according to the monitoring data of the nuclear power plant; the isolation measures include starting the safety barrier inside the nuclear power plant and limiting the approach of unnecessary personnel, and using remote control technology to perform high-risk operations.
[0067] The isolation measures of the embodiment include activating the safety barriers within the nuclear power plant and limiting the access of non-essential personnel, using remote control technology to perform high-risk operations to reduce direct exposure of personnel to potentially dangerous environments.
[0068] As an implementation, a detailed isolation plan is prepared in advance, including procedures for activating safety barriers, scope and procedures for limiting personnel access, and guidelines for using remote control technology; when activating isolation measures, activate safety barriers in the control system, confirm that safety barriers have been properly activated and are in normal working condition through sensors and monitoring systems; send evacuation or distancing instructions to all non-essential personnel through the integrated communication system, ensure that the personnel understand the isolation area and evacuation route, set up an isolation area around the nuclear power plant and deploy security personnel or obstacles to limit access; ensure that all remote control devices and systems are in good condition and ready for use, and perform high-risk operations using remote control technology; real-time monitoring of the isolation area and high-risk operations through remote control devices and sensors, and maintaining communication with all relevant personnel through the integrated communication system to provide real-time information and guidance; dynamically adjust isolation measures and remote control operations based on monitoring data and accident development to maximize safety; during the accident handling process, adjust and optimize the isolation and remote control operation process according to the actual situation to improve efficiency and safety.
[0069] Step S106, through the communication link with the outside, information sharing and coordinated action; and continuously record all key decisions and operations; and accident assessment and nuclear power plant operation recovery.
[0070] As an implementation, the method of establishing a communication link between the nuclear power plant and the outside includes: identifying the external emergency services, government agencies and related organizations that need to communicate; determining the communication means according to the needs, such as telephone, radio, satellite communication, etc.; develop communication protocols, including communication frequency, data format, information confirmation method, etc.; test the communication link, that is, before actual use, test the communication link to ensure its reliability and stability.
[0071] Thus, through the communication link with external emergency services, government agencies and other related organizations, to ensure information sharing and coordinated action. Including through the established communication link, timely sending accident information and handling progress to external emergency services, government agencies and related organizations. Coordinate with these external agencies and organizations to jointly develop and implement accident response plans. Receive feedback information from these agencies and organizations for adjusting and optimizing accident response measures. Maintain continuous communication with these agencies and organizations during the accident handling process to ensure the accuracy and timeliness of information.
[0072] During the incident handling process, all key decisions and operations need to be continuously recorded to provide data support for post-incident evaluation and improvement. After the incident is under control, environmental monitoring and decontamination operations are performed, the structural and equipment integrity of the nuclear power plant is evaluated, and a recovery plan is developed.
[0073] As an implementation, an incident handling record system is established to record all key decisions and operations during the emergency handling process of the incident. For example, during the incident handling process, information such as key decisions, operation steps, time, and personnel performing the operation is recorded and saved in real time. The recorded data is securely stored to prevent data loss or damage.
[0074] In some embodiments, the method further includes evaluating the effectiveness and efficiency of the incident response, evaluating the impact of the incident on the surrounding environment and developing a decontamination plan based on environmental monitoring data, evaluating the structural and equipment integrity of the nuclear power plant based on the operating parameters of the equipment, determining the equipment or structure that needs to be repaired or replaced, developing a recovery plan for the nuclear power plant based on the evaluation results of the structural and equipment integrity of the nuclear power plant, and implementing the recovery plan including repair work, re-activation procedures, and safety testing.
[0075] That is, after the incident handling is completed, a post-incident audit is performed to analyze the recorded data and evaluate the effectiveness and efficiency of the incident response. After the incident is under control, environmental monitoring is immediately carried out to evaluate the impact of the incident on the surrounding environment. Based on the environmental monitoring results, a decontamination plan is developed and decontamination operations are carried out to eliminate the consequences of the incident. The structural and equipment integrity of the nuclear power plant is evaluated to determine which parts need to be repaired or replaced. Based on the evaluation results, a recovery plan for the nuclear power plant is developed, including repair work, re-activation procedures, and safety testing. The recovery plan is gradually implemented to ensure that the safety and functionality of the nuclear power plant are fully restored.
[0076] Thus, through the above operations, the nuclear power plant can effectively communicate and coordinate with external emergency services, government agencies, and other relevant organizations during the incident handling process, ensuring information sharing and action consistency. At the same time, by recording key decisions and operations, data support is provided for post-incident evaluation and improvement. Finally, after the incident is under control, environmental monitoring and decontamination operations are performed, the structural and equipment integrity of the nuclear power plant is evaluated, and a recovery plan is developed to fully restore the normal operation of the nuclear power plant.
[0077] To implement the above embodiments, the present application also proposes a nuclear power plant incident emergency command device. Figure 3 A block diagram of a nuclear power plant incident emergency command device according to an embodiment of the present application is shown in FIG. 1. Figure 3 As shown in FIG. 1, the nuclear power plant incident emergency command device can include a data acquisition module 201, an incident diagnosis module 202, an incident alarm module 203, and a strategy generation module 204.
[0078] The data acquisition module 201 is configured to acquire real-time key safety parameters of the nuclear power plant.
[0079] The accident diagnosis module 202 is configured to acquire operation data of the nuclear power plant when the key safety parameters exceed the safety threshold range, and perform accident diagnosis on the operation data to obtain an accident diagnosis result.
[0080] The accident alarm module 203 is configured to generate alarm information according to the accident diagnosis result, and send the alarm information according to a sending rule of the alarm information.
[0081] The strategy generation module 204 is configured to predict a plurality of predicted accident development results of the accident development according to the accident diagnosis result, and generate a plurality of coping schemes according to the plurality of predicted accident development results.
[0082] Further, in a possible implementation manner of the embodiment of the present application, the key safety parameters include temperature data of a reactor core and a surrounding area, pressure data in the reactor, radiation dose rates of a plurality of key positions of the nuclear power plant, and a plurality of index data of a cooling system, wherein the plurality of index data of the cooling system include flow rate, temperature and pressure of the coolant; the temperature data is collected by a plurality of temperature collection devices deployed in the reactor core and the surrounding area; the pressure data is obtained by periodically detecting the pressure in the reactor by a pressure sensor; the radiation dose rates are collected by a plurality of radiation detectors respectively deployed at the plurality of key positions of the nuclear power plant; and the plurality of index data of the cooling system are collected by a flow meter, a temperature sensor and a pressure sensor respectively deployed on the cooling system.
[0083] Further, in a possible implementation manner of the embodiment of the present application, the accident diagnosis module 202 is specifically configured to:
[0084] acquire operation data of the nuclear power plant when the key safety parameters exceed the safety threshold range;
[0085] input the operation data of the nuclear power plant into a trained decision tree, perform accident prediction and evaluation according to a branch rule of the decision tree, and obtain the accident diagnosis result.
[0086] Further, in a possible implementation manner of the embodiment of the present application, the accident diagnosis module 202 is further configured to:
[0087] measure the uncertainty or the degree of disorder of the data in the operation data of the nuclear power plant by using a method of calculating information entropy and conditional entropy.
[0088] Further, in a possible implementation manner of the embodiment of the present application, the accident diagnosis module 202 is further configured to:
[0089] Obtain a training data set, the training data set including historical operation data, sensor data and accident record data of the nuclear power plant;
[0090] Clean, normalize and discretize the data set in the training data set to obtain a sample data set;
[0091] Construct a decision tree according to the sample data set;
[0092] Evaluate the performance of the decision tree using a cross-validation method.
[0093] Further, in a possible implementation manner of the embodiment of the present application, the strategy generation module 204 is further used for:
[0094] According to the response plan, implement isolation measures; and adjust the isolation measures in real time according to the monitoring data of the nuclear power plant; the isolation measures include starting the safety barrier inside the nuclear power plant, limiting the approach of unnecessary personnel and adopting remote control technology to perform high-risk operations.
[0095] Further, in a possible implementation manner of the embodiment of the present application, the strategy generation module 204 is further used for:
[0096] Share information and coordinate actions with external personnel through a communication link with the outside;
[0097] Continuously record all key decisions and operations.
[0098] Further, in a possible implementation manner of the embodiment of the present application, the strategy generation module 204 is further used for:
[0099] Evaluate the effect and efficiency of the accident response;
[0100] According to the environmental monitoring data, evaluate the influence of the accident on the surrounding environment and develop a decontamination plan;
[0101] According to the nuclear power plant equipment operation parameters, evaluate the structure and equipment integrity of the nuclear power plant, and determine the equipment or structure that needs to be repaired or replaced;
[0102] According to the evaluation result of the structure and equipment integrity of the nuclear power plant, develop a recovery plan for the nuclear power plant; the recovery plan includes repair work, re-enabling procedures and safety tests.
[0103] It should be noted that the foregoing explanation and description of the nuclear power plant accident emergency command method embodiment are also applicable to the nuclear power plant accident emergency command device of the embodiment, which will not be described here.
[0104] In order to realize the above-mentioned embodiments, the present application further provides an electronic device. Please refer to Figure 4 , Figure 4 is a block diagram of an electronic device provided by the embodiment of the present application. As shown inFigure 4 As shown in FIG. 3, the electronic device 300 includes a processor 301 and a memory 302 connected with the processor 301 in communication; the memory 302 stores computer-executable instructions; and the processor 301 executes the computer-executable instructions stored in the memory to implement the method provided by the foregoing embodiments.
[0105] To implement the above-described embodiments, the present application further provides a computer-readable storage medium, which stores computer-executable instructions, and the computer-executable instructions are executed by a processor to implement the method provided by the foregoing embodiments.
[0106] To implement the above-described embodiments, the present application further provides a computer program product, which includes a computer program, and the computer program is executed by a processor to implement the method provided by the foregoing embodiments.
[0107] In the foregoing embodiment description, the description of the terms "one embodiment", "some embodiments", "an example", "a specific example", or "some examples" means that the specific features, structures, materials or characteristics described in connection with the embodiment or example are included in at least one embodiment or example of the present application. In the present description, the illustrative description of the above terms does not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials or characteristics described can be combined in any appropriate manner in any one or more embodiments or examples. In addition, the person skilled in the art can combine and combine the different embodiments or examples described in the present description and the features of the different embodiments or examples without contradiction.
[0108] In addition, the terms "first", "second" are only for descriptive purposes, and cannot be understood as indicating or implying relative importance or implicitly indicating the number of the indicated technical features. Therefore, the features defined with "first", "second" can explicitly or implicitly include at least one of the features. In the description of the present application, the meaning of "a plurality of" is at least two, for example, two, three, etc., unless otherwise explicitly specified.
[0109] Although the embodiments of the present application have been shown and described above, it should be understood that the above-described embodiments are exemplary and cannot be understood as limiting the present application, and the person skilled in the art can make changes, modifications, replacements and variations to the above-described embodiments within the scope of the present application.
Claims
1. A nuclear power plant accident emergency command method, characterized in that: The following steps are involved: Obtain real-time key safety parameters of nuclear power plants; When the key safety parameter exceeds the safety threshold range, obtaining nuclear power plant operation data to perform accident diagnosis and obtain accident diagnosis results; the accident diagnosis results include predicted accident type, accident severity and response measures; Generate alarm information according to the accident diagnosis result, and send the alarm information according to the alarm information sending rules; Based on the accident diagnosis result, multiple predicted accident development results are predicted; and based on the multiple predicted accident development results, multiple response plans are generated.
2. The method according to claim 1, characterized in that The key safety parameters include temperature data of the reactor core and surrounding areas, pressure data inside the reactor, radiation dose rates at multiple key locations of the nuclear power plant, and multiple indicator data of the cooling system, wherein the multiple indicator data of the cooling system include the flow rate, temperature, and pressure of the coolant; the temperature data is collected by multiple temperature acquisition devices deployed in the reactor core and surrounding areas; the pressure data is obtained by regularly detecting the pressure inside the reactor through a pressure sensor; the radiation dose rate is collected by multiple radiation detectors deployed at multiple key locations of the nuclear power plant; the multiple indicator data of the cooling system are collected respectively by flow meters, temperature sensors, and pressure sensors deployed on the cooling system.
3. The method according to claim 1, characterized in that When the key safety parameter exceeds the safety threshold range, obtaining nuclear power plant operation data for accident diagnosis to obtain an accident diagnosis result; including: When the key safety parameter exceeds the safety threshold range, obtaining nuclear power plant operation data; The nuclear power plant operation data is input into a trained decision tree, and accident prediction and evaluation are performed according to the branching rules of the decision tree to obtain accident diagnosis results.
4. The method according to claim 3, characterized in that Before inputting the nuclear power plant operation data into the trained decision tree, the following steps are performed: The uncertainty or confusion degree of the data in the nuclear power plant operation data is measured by calculating information entropy and conditional entropy.
5. The method according to claim 3, characterized in that The decision tree construction method comprises: Acquire a training data set, wherein the training data set includes historical operation data, sensor data, and accident record data of the nuclear power plant; Cleaning, normalizing, and discretizing the data set in the training data set to obtain a sample data set; Constructing a decision tree based on the sample data set; The performance of the decision tree was evaluated using a cross-validation method.
6. The method according to claim 1, characterized in that After generating multiple response plans, including: Isolation measures are implemented according to the response plan and adjusted in real time based on the monitoring data of the nuclear power plant. The isolation measures include activating safety barriers inside the nuclear power plant, restricting the access of non-essential personnel, and using remote control technology to perform high-risk operations.
7. The method according to claim 1, characterized in that After generating multiple response plans, the following steps are also included: Share information and coordinate actions with external personnel through external communication links; Maintain a record of all key decisions and actions.
8. The method according to claim 1, characterized in that The method further comprises: Evaluate the effectiveness and efficiency of incident response; Assess the impact of the accident on the surrounding environment and develop a decontamination plan based on environmental monitoring data; Evaluate the structural and equipment integrity of the nuclear power plant based on the operating parameters of the nuclear power plant equipment and determine the equipment or structures that need to be repaired or replaced; A nuclear power plant recovery plan is developed based on the assessment results of the structural and equipment integrity of the nuclear power plant; the recovery plan includes repair work, recommissioning procedures and safety testing.
9. A nuclear power plant accident emergency command device, characterized in that: include: Data acquisition module, used to obtain real-time key safety parameters of nuclear power plants; An accident diagnosis module is configured to obtain nuclear power plant operation data for accident diagnosis when the key safety parameter exceeds the safety threshold range, and obtain an accident diagnosis result; the accident diagnosis result includes a predicted accident type, accident severity, and response measures; An accident alarm module is used to generate an alarm message according to the accident diagnosis result and send the alarm message according to the alarm message sending rule; The strategy generation module is used to predict multiple predicted accident development results based on the accident diagnosis results; and generate multiple response plans based on the multiple predicted accident development results.
10. An electronic device, characterized in that: include: a processor, and a memory communicatively connected to the processor; The memory stores computer-executable instructions; The processor executes the computer-executable instructions stored in the memory to implement the method according to any one of claims 1 to 8.