Nuclear power plant accident control method, device and system

Abstract

The present disclosure relates to a method, apparatus and system for controlling nuclear power plant accidents. Among them, the method includes: obtaining operation data of nuclear power equipment within a preset time period, selecting target data that changes over time from the operation data, generating a target sequence of the target data using the target data, identifying whether an accident has occurred based on the target sequence and the operation data to obtain an identification result, generating multiple accident mitigation strategies using the operation data and the identification result, performing index evaluation on the multiple accident mitigation strategies to obtain an index evaluation value, selecting the accident mitigation strategy with the highest index evaluation value from the multiple accident mitigation strategies to obtain a target accident mitigation strategy, inputting the target accident mitigation strategy into a nuclear power accident simulation model for simulation to obtain a simulation result, and executing the target accident mitigation strategy when the simulation result meets the preset conditions. This solution can improve the accuracy and efficiency of executing accident mitigation strategies.

Description

Technical Field

[0001] The present disclosure relates to the technical field of nuclear power plants, and in particular to a method, device, and system for managing and controlling nuclear power plant accidents. Background Art

[0002] In relevant technologies, a severe nuclear power plant accident refers to an incident in which the reactor core is severely damaged, potentially compromising the integrity of the containment, leading to environmental radioactive contamination, casualties, and significant losses. In the event of a severe accident, nuclear power plant operators and emergency technical support personnel should follow clear action guidelines and quickly develop appropriate response strategies and mitigation measures to minimize the release of radioactive materials, protect the integrity of the containment, and, as far as possible, restore the core to a controlled and stable state. However, in practice, severe accident management at nuclear power plants still primarily focuses on identifying and implementing mitigation measures, resulting in low efficiency and difficulty in timely accident control. Summary of the Invention

[0003] To overcome the problems existing in the related art, the present disclosure provides a nuclear power plant accident management method, device and system.

[0004] According to a first aspect of an embodiment of the present disclosure, a method for managing and controlling a nuclear power plant accident is provided, comprising:

[0005] Acquiring operating data of nuclear power equipment within a preset time period; the preset time period is a time period of a preset length before the current moment;

[0006] Selecting target data that changes over time from the operating data, and generating a target sequence of the target data using the target data;

[0007] identifying whether an accident occurs based on the target sequence and the operating data, and obtaining an identification result;

[0008] If the identification result indicates that an accident has occurred, generating a plurality of accident mitigation strategies using the operating data and the identification result;

[0009] Performing an index evaluation on the multiple accident mitigation strategies to obtain an index evaluation value;

[0010] Selecting the accident mitigation strategy with the highest indicator evaluation value from the multiple accident mitigation strategies to obtain a target accident mitigation strategy;

[0011] Inputting the target accident mitigation strategy into a nuclear power accident simulation model for simulation to obtain simulation results;

[0012] When the simulation result meets the preset conditions, the target accident mitigation strategy is executed.

[0013] In some embodiments of the present application, selecting target data that changes over time from the operation data and generating a target sequence of the target data includes:

[0014] Selecting the pressure data and the core makeup flow rate data of the reactor coolant system within the preset time period from the operation data to obtain the target data;

[0015] Generating a first target sequence of the pressure data; the pressure data in the first target data is sorted according to the pressure data acquisition time;

[0016] Identifying whether an accident has occurred based on the target sequence and the operation data to obtain an identification result, including:

[0017] Determining the pressure value change rate according to the first target sequence;

[0018] When it is determined that the pressure change amount changes from a first fluctuation state to a second fluctuation state within the preset time period, and the core makeup flow rate starts to decrease from the maximum flow rate value within the preset time period, it is determined that the core is flooded to obtain the identification result; the first fluctuation state is that the pressure value change rate is greater than or equal to a first change amount; the second fluctuation state is that the pressure value change rate is less than or equal to a second change amount; the first change rate is greater than the second change rate.

[0019] In some embodiments of the present application, selecting target data that changes over time from the operation data and generating a target sequence of the target data includes:

[0020] Obtaining the channel information of the containment energy release heat sink within the preset time period and the radiation dose data of the containment within the preset time period from the operation data;

[0021] Generating a second target sequence of the radiation dose data; the radiation dose data in the second target data is sorted according to the radiation dose data acquisition time;

[0022] Identifying whether an accident has occurred based on the target sequence and the operation data to obtain an identification result, including:

[0023] Determining whether there are multiple outliers in the channel information and determining whether the energy release heat sink can dissipate heat normally according to the operation data;

[0024] Obtaining the hydrogen concentration value inside the containment from the operation data, determining whether the hydrogen concentration value inside the containment falls within a preset safety threshold, and determining whether the radiation dose data shows an increasing trend over time according to the second target sequence;

[0025] In the case where there are multiple outliers in the radiation dose data and the heat sink for energy release cannot dissipate heat normally, and / or in the case where the hydrogen concentration value in the containment does not fall within the preset safety threshold and the radiation dose data shows a continuous upward trend over time, it is determined that the containment is abnormal, and the recognition result is obtained.

[0026] In some embodiments of the present application, after obtaining the target accident mitigation strategy from the accident mitigation strategy with the highest index evaluation value among the multiple accident mitigation strategies, it further includes:

[0027] Display the target accident mitigation strategy on the terminal device;

[0028] In response to receiving a modification instruction for the target parameter from the user, compare the modification value of the target parameter with the preset constraint conditions; the modification instruction includes the modification value;

[0029] In the case where the modification value meets the preset constraint conditions, modify the target parameter in the target accident mitigation strategy according to the modification instruction;

[0030] In response to recognizing the first parameter associated with the target parameter, modify the first parameter according to the preset modification method and the modification value so that the first parameter is adapted to the target parameter.

[0031] In some embodiments of the present application, executing the target accident mitigation strategy includes:

[0032] Determine the operation type of each operation in the target accident mitigation strategy; the operation type includes a first operation and a second operation; the first operation is an operation automatically executed by a computer; the second operation is an operation that requires manual intervention;

[0033] Execute the following steps according to the operation execution order in the target accident mitigation strategy:

[0034] Determine the operation type of the current operation;

[0035] In response to the current operation being the execution of the first operation, control the target device to execute the first operation;

[0036] In response to the currently executed operation being the second operation, monitor whether the user has completed the second operation;

[0037] In the case where it is monitored that the user has completed the second operation, update the next operation to the current operation, and return to execute the step of determining the operation type of the current operation until all operations in the target accident mitigation strategy are completed.

[0038] According to a second aspect of the embodiments of the present disclosure, a nuclear power plant accident control device is provided, including:

[0039] An acquisition unit, configured to acquire operation data of nuclear power equipment within a preset time period; the preset time period is a time period with a preset duration before the current moment;

[0040] A first selection unit, configured to select target data that changes with time from the operation data, and generate a target sequence of the target data by using the target data;

[0041] An identification unit, configured to identify whether an accident occurs based on the target sequence and the operation data, and obtain an identification result;

[0042] A generation unit, configured to generate a plurality of accident mitigation strategies by using the operation data and the identification result in the case that the identification result indicates an accident;

[0043] An evaluation unit, configured to perform index evaluation on the plurality of accident mitigation strategies to obtain an index evaluation value;

[0044] A second selection unit, configured to select the accident mitigation strategy with the highest index evaluation value from the plurality of accident mitigation strategies to obtain a target accident mitigation strategy;

[0045] A simulation unit, configured to input the target accident mitigation strategy into a nuclear power accident simulation model for simulation to obtain a simulation result;

[0046] An execution unit, configured to execute the target accident mitigation strategy in the case that the simulation result meets a preset condition.

[0047] In some embodiments of the present application, the first selection unit is specifically configured to:

[0048] Select the pressure data and the core makeup flow data of the reactor coolant system within the preset time period from the operation data to obtain the target data;

[0049] Generate a first target sequence of the pressure data; the pressure data in the first target data is sorted according to the pressure data acquisition time;

[0050] The identifying whether an accident occurs based on the target sequence and the operation data to obtain an identification result includes:

[0051] Determine a pressure value change rate according to the first target sequence;

[0052] When it is determined that the pressure change amount changes from the first fluctuation state to the second fluctuation state within the preset time period, and the core makeup flow rate starts to decrease from the maximum flow rate value within the preset time period, it is determined that the core is flooded, and the recognition result is obtained; the first fluctuation state is that the pressure value change rate is greater than or equal to the first change amount; the second fluctuation state is that the pressure value change rate is less than or equal to the second change amount; the first change rate is greater than the second change rate.

[0053] According to a third aspect of the embodiments of the present disclosure, an electronic device includes: a memory, a processor, and a computer program stored on the memory and executable on the processor. When the processor executes the computer program, the method according to any one of the first aspects is implemented.

[0054] According to a fourth aspect of the embodiments of the present disclosure, a computer-readable storage medium is provided, on which a computer program is stored. When the computer program is executed by a processor, the method according to any one of the first aspects is implemented.

[0055] According to a fifth aspect of the embodiments of the present disclosure, a computer program product is provided, including a computer program. When the computer program is executed by a processor, the method according to any one of the first aspects is implemented.

[0056] The technical solutions provided by the embodiments of the present disclosure may include the following beneficial effects: By obtaining the operation data of nuclear power equipment within a preset time period, selecting target data that changes with time from the operation data, generating a target sequence of the target data using the target data, identifying whether an accident occurs based on the target sequence and the operation data to obtain an identification result, in the case where the identification result is that an accident occurs, generating multiple accident mitigation strategies using the operation data and the identification result, performing index evaluation on the multiple accident mitigation strategies to obtain an index evaluation value, selecting the accident mitigation strategy with the highest index evaluation value from the multiple accident mitigation strategies to obtain a target accident mitigation strategy, inputting the target accident mitigation strategy into a nuclear power accident simulation model for simulation to obtain a simulation result, and executing the target accident mitigation strategy when the simulation result meets the preset conditions. By generating multiple accident mitigation strategies using the operation data and the identification result, selecting the target accident mitigation strategy with the highest index evaluation value for simulation, and executing the target accident mitigation strategy when the simulation result meets the conditions, it is possible to improve the accuracy and efficiency of the execution of the accident mitigation strategy on the premise of improving the generation efficiency of the accident mitigation strategy.

[0057] It should be understood that the above general description and the following detailed description are only exemplary and explanatory, and cannot limit the present disclosure. Description of the Drawings

[0058] The accompanying drawings here are incorporated into the specification and form a part of this specification, showing embodiments consistent with the present invention, and are used together with the specification to explain the principles of the present invention.

[0059] Figure 1 is a flowchart of a method for controlling nuclear power plant accidents shown according to an exemplary embodiment.

[0060] Figure 2 is a block diagram of a device for controlling nuclear power plant accidents shown according to an exemplary embodiment.

[0061] Figure 3 is a block diagram of a device for a method for controlling nuclear power plant accidents shown according to an exemplary embodiment. Detailed implementation manners

[0062] Here, the exemplary embodiments will be described in detail, and the examples are shown in the accompanying drawings. When the following description refers to the accompanying drawings, unless otherwise indicated, the same numbers in different drawings represent the same or similar elements. The implementation manners described in the following exemplary embodiments do not represent all implementation manners consistent with the present invention. On the contrary, they are merely examples of devices and methods consistent with some aspects of the present invention as detailed in the appended claims.

[0063] The terms used in the embodiments of the present disclosure are only for the purpose of describing specific embodiments, and are not intended to limit the embodiments of the present disclosure. The singular forms "a" and "the" used in the embodiments of the present disclosure and the appended claims are also intended to include the plural forms, unless the context clearly indicates otherwise.

[0064] It should be understood that although the terms first, second, third, etc. may be used in the embodiments of the present disclosure to describe various information, these information should not be limited to these terms. These terms are only used to distinguish the same type of information from each other. For example, without departing from the scope of the embodiments of the present disclosure, the first information may also be referred to as the second information, and similarly, the second information may also be referred to as the first information. Depending on the context, the words "if" and "when" as used herein may be interpreted as "when...", "when...", or "in response to determining".

[0065] In addition, various forms of processes shown in the embodiments of the present disclosure can be used, reordering, adding, or deleting steps. For example, the steps described in the present application can be executed in parallel, sequentially, or in a different order, as long as the desired results of the technical solutions disclosed in the present application can be achieved. This is not limited herein.

[0066] In the related art, a severe accident in a nuclear power plant refers to an accident in which the reactor core of the nuclear power plant is severely damaged and may damage the integrity of the containment, resulting in environmental radioactive contamination and personal injury and death, causing huge losses. Nuclear power plant operators and emergency technical support personnel should, in the event of a severe accident, quickly formulate appropriate response strategies and accident mitigation measures based on clear action guidelines to reduce the release of radioactive substances, protect the integrity of the containment, and restore the reactor core to a controlled and stable state as much as possible. A severe accident in a nuclear power plant refers to an accident in which the reactor core of the nuclear power plant is severely damaged and may damage the integrity of the containment, resulting in environmental radioactive contamination and personal injury and death, causing huge losses. Nuclear power plant operators and emergency technical support personnel should, in the event of a severe accident, quickly formulate appropriate response strategies and accident mitigation measures based on clear action guidelines to reduce the release of radioactive substances, protect the integrity of the containment, and restore the reactor core to a controlled and stable state as much as possible. However, in the practical application of severe accident management in nuclear power plants, it is still mostly used to determine and implement mitigation measures, resulting in low efficiency and difficulty in controlling accidents in a timely manner.

[0067] To solve the above problems, the present disclosure provides a nuclear power plant accident control method, device and system. By obtaining the operation data of nuclear power equipment within a preset time period, selecting target data that changes with time from the operation data, generating a target sequence of the target data using the target data, identifying whether an accident has occurred based on the target sequence and the operation data to obtain an identification result, in the case where the identification result indicates that an accident has occurred, generating multiple accident mitigation strategies using the operation data and the identification result, evaluating the indicators of the multiple accident mitigation strategies to obtain an indicator evaluation value, selecting the accident mitigation strategy with the highest indicator evaluation value from the multiple accident mitigation strategies to obtain a target accident mitigation strategy, inputting the target accident mitigation strategy into a nuclear power accident simulation model for simulation to obtain a simulation result, and in the case where the simulation result meets the preset conditions, implementing the target accident mitigation strategy. By generating multiple accident mitigation strategies using the operation data and the identification result, selecting the target accident mitigation strategy with the highest indicator evaluation value for simulation, and implementing the target accident mitigation strategy in the case where the simulation result meets the conditions, it is possible to improve the accuracy and efficiency of the implementation of the accident mitigation strategy on the premise of improving the generation efficiency of the accident mitigation strategy.

[0068] Figure 1 is a flowchart of a nuclear power plant accident control method shown according to an exemplary embodiment. As Figure 1 shown, it should be noted that the nuclear power plant accident control method of the embodiments of the present application is applied to a nuclear power plant accident control device. As Figure 1 shown, the method may include the following steps:

[0069] Step 101, obtain the operation data of nuclear power equipment within a preset time period.

[0070] Among them, the preset time period is the time period of the preset duration before the current moment.

[0071] It should be noted that in order to more accurately identify whether an accident occurs, it is not only necessary to identify based on the operation data collected at the current moment, but also necessary to evaluate based on the data within a period of time before the current time node as a whole, so as to be able to identify the data change situation within a period of time, and then improve the accuracy of accident identification.

[0072] Step 102: Select target data that changes with time from the operation data, and generate a target sequence of the target data.

[0073] In one embodiment, data whose values change with time can be selected from the operation data as target data, and a target sequence is generated using the target data.

[0074] In one embodiment, the target data in the target sequence can be sorted according to the data collection time.

[0075] In some embodiments of the present application, step 102 may specifically include the following steps: Select the pressure data and the core makeup flow rate data of the reactor coolant system within the preset time period from the operation data to obtain the target data; generate a first target sequence of the pressure data.

[0076] Among them, the pressure data in the first target data is sorted according to the pressure data collection time;

[0077] Step 103 may specifically include: Determine the pressure value change rate according to the first target sequence; when it is determined that the pressure change amount changes from the first fluctuation state to the second fluctuation state within the preset time period, and the core makeup flow rate starts to decrease from the maximum flow rate value within the preset time period, determine that the core is flooded to obtain the recognition result.

[0078] Among them, the first fluctuation state is that the pressure value change rate is greater than or equal to the first change amount; the second fluctuation state is that the pressure value change rate is less than or equal to the second change amount; the first change rate is greater than the second change rate.

[0079] In one embodiment, it is possible to determine whether the core is flooded according to the relationship between the pressure change trend of the reactor coolant system and the core makeup flow rate. When the coolant pressure changes from a violent fluctuation (for example, the numerical change rate of the coolant pressure is greater than 10%) to a stable and slow change (for example, the numerical change rate of the coolant pressure is less than 1%), and the makeup flow rate gradually decreases from the maximum flow rate, it can be determined that the core is flooded. Compared with simply relying on the value of the in-containment water level sensor to determine whether the core is flooded, the accuracy is higher.

[0080] In some other embodiments of the present application, step 102 may specifically include the following steps:

[0081] Obtain the channel information of the containment energy release heat sink in a preset time period from the operation data, as well as the radiation dose data of the containment in the preset time period;

[0082] Generate a second target sequence of the radiation dose data; the radiation dose data in the second target data is sorted according to the radiation dose data acquisition time;

[0083] Step 103 may specifically include:

[0084] Determine whether there are multiple outliers in the channel information, and determine whether the energy release heat sink can remove heat normally according to the operation data;

[0085] Obtain the hydrogen concentration value inside the containment from the operation data, determine whether the hydrogen concentration value inside the containment falls within a preset safety threshold, and determine whether the radiation dose data shows an increasing trend over time according to the second target sequence;

[0086] In the case where there are multiple outliers in the radiation dose data and the energy release heat sink cannot remove heat normally, and / or in the case where the hydrogen concentration value inside the containment does not fall within the preset safety threshold and the radiation dose data shows a continuously increasing trend over time, determine that the containment is abnormal to obtain the identification result.

[0087] In the embodiments of the present application, it is possible to determine whether the energy release heat sink can remove heat normally by checking whether the heat removal rate of the energy release heat sink meets the standard in the operation data.

[0088] In one embodiment, it is possible to determine whether the channel data of the containment energy release heat sink is continuously abnormal and cannot remove heat normally, or whether the hydrogen concentration inside the containment exceeds the safety range and the radiation dose level inside the containment continues to increase significantly. In the case where there are multiple outliers in the radiation dose data and the energy release heat sink cannot remove heat normally, and / or in the case where the hydrogen concentration value inside the containment does not fall within the preset safety threshold and the radiation dose data shows a continuously increasing trend over time, determine that the containment is abnormal.

[0089] In some embodiments of the present application, it is also possible to obtain the core safety injection system flow rate and the total water inventory of the heat release loop in the reactor from the operation data. When the core safety injection system flow rate continuously remains lower than the low flow rate set value F and the total water inventory of the primary loop is less than the low water inventory set value M, it can be determined that the core is in a bare state, without waiting until the core temperature reaches 650 degrees Celsius or the fuel rod cladding temperature reaches 800 degrees Celsius to determine the core is in a bare state. The low flow rate set value F of the safety injection system and the three-dimensional total water inventory value M of the heat release loop in the reactor are in a linear inverse relationship, and the larger the F value, the smaller the M value.

[0090] In some embodiments of the present application, the integrity and controllability of the containment can be judged in the following ways: 1. The heat sink channels for the energy release of the containment are available, and the sensor data in the heat sink channels are valid and without abnormalities; 2. The physical integrity of the containment boundary is maintained, and the pressure at the containment boundary is normal; 3. The hydrogen concentration inside the containment is within a safe range and does not reach the combustible concentration; if all the above three conditions are met, it can be determined that the containment is intact and controllable, and there is no need to rely on manual system inspection for confirmation.

[0091] In some embodiments of the present application, the water injection method can also be automatically selected according to the decay heat to be removed and combined with the current working conditions. When there is no break in the heat release loop in the reactor, the direct water injection method of the coolant system is preferred. If the decay heat removed by this method still cannot meet the requirements, the water injection method of the containment sump recirculation and the water injection method of the secondary side of the steam generator are automatically superimposed and started without manual intervention. If a break occurs in the heat release loop in the reactor, the water injection method of the containment sump recirculation is directly adopted. If the decay heat removed by this method is still insufficient, the water injection method to the secondary side of the steam generator can also be automatically superimposed as a supplementary method.

[0092] Step 103: Identify whether an accident has occurred based on the target sequence and operation data to obtain an identification result.

[0093] Step 104: In the case where the identification result indicates that an accident has occurred, generate multiple accident mitigation strategies using the operation data and the identification result.

[0094] Step 105: Evaluate the indicators of the multiple accident mitigation strategies to obtain an indicator evaluation value.

[0095] In the embodiments of the present application, the above-mentioned indicator evaluation value can be calculated according to a preset indicator calculation method, which is used to evaluate the mitigation effect of the accident mitigation strategy.

[0096] Step 106: Select the accident mitigation strategy with the highest indicator evaluation value from the multiple accident mitigation strategies to obtain a target accident mitigation strategy.

[0097] It can be understood that in order to find a better accident mitigation strategy, multiple feasible accident mitigation strategies can be generated, evaluated, and the accident mitigation strategy with the highest indicator evaluation value is used as the target accident mitigation strategy, thereby improving the quality of the accident mitigation strategy.

[0098] In some other embodiments of the present application, after step 106, the method may further include the following steps:

[0099] Display the target accident mitigation strategy on the terminal device;

[0100] In response to receiving a modification instruction of a target parameter from a user, compare the modified value of the target parameter with a preset constraint condition; the modification instruction includes the modified value.

[0101] When the modified value meets the preset constraint condition, modify the target parameter in the target accident mitigation strategy according to the modification instruction.

[0102] In response to identifying a first parameter associated with the target parameter, modify the first parameter according to a preset modification method and the modified value, so that the first parameter is adapted to the target parameter.

[0103] In the embodiment of the present application, in order to improve the rationality of the target accident mitigation strategy, the target accident mitigation strategy can be displayed on a terminal device so that the user can review and adjust the target accident mitigation strategy.

[0104] In one embodiment, after receiving a modification instruction of a target parameter from a user, the modified value of the target parameter can be compared with a preset constraint condition, that is, it is determined whether the modified value input by the user meets the requirements, so as to avoid problems with the target accident mitigation strategy after modification due to the user inputting data that does not meet the requirements.

[0105] When it is determined that the modified value meets the preset constraint condition, modify the target parameter in the target accident mitigation strategy according to the modification instruction.

[0106] It should be noted that the above constraint conditions can be preset according to the characteristics of the above target parameter and actual requirements. The modified value can be controlled within a reasonable range through the constraint conditions.

[0107] It can be understood that in the case of a nuclear power accident that has already occurred, time is very precious, and the earlier the accident mitigation strategy is executed, the more losses caused by the accident can be reduced. Therefore, in a relatively urgent situation, a first parameter associated with the above target parameter can be identified, and the first parameter can be modified according to a preset modification method and the modified value, so that the first parameter is adapted to the target parameter. Thus, in an emergency situation, the target accident mitigation strategy can be quickly modified, which improves the efficiency and accuracy of parameter modification compared with relying on manual modification of all parameters, and further improves the speed of executing the accident mitigation strategy.

[0108] Step 107: Input the target accident mitigation strategy into a nuclear power accident simulation model for simulation to obtain a simulation result.

[0109] Step 108: When the simulation result meets the preset condition, execute the target accident mitigation strategy.

[0110] It can be understood that the target accident mitigation strategy can be used to simulate the strategy execution process to determine whether the target accident mitigation strategy is feasible, that is, when the simulation result meets the preset conditions, the target accident mitigation strategy is executed.

[0111] In some other embodiments of the present application, step 108 may specifically include the following steps:

[0112] Determine the operation type of each operation in the target accident mitigation strategy; the operation type includes a first operation and a second operation; the first operation is an operation automatically executed by a computer; the second operation is an operation that requires manual intervention;

[0113] Execute the following steps according to the operation execution order in the target accident mitigation strategy:

[0114] Determine the operation type of the current operation;

[0115] In response to the current operation being the execution of the first operation, control the target device to execute the first operation;

[0116] In response to the currently executed operation being the second operation, monitor whether the user has completed the second operation;

[0117] In the case where it is monitored that the user has completed the second operation, update the next operation to the current operation, and return to execute the step of determining the operation type of the current operation until all operations in the target accident mitigation strategy are completed.

[0118] It can be understood that since there may be both operations automatically executed by a computer and operations that require manual intervention in the target accident mitigation strategy, the operations executed by the computer are controllable, while there are uncontrollable factors in the operations that require manual intervention. Therefore, in order to improve the execution efficiency, the automation of the target accident mitigation strategy can be further enhanced.

[0119] In one embodiment, in order to further improve the execution efficiency of the target accident mitigation strategy, during the process of executing operations according to the operation steps in the target accident mitigation strategy, if the current execution step is the second operation, that is, the operation that requires manual intervention, it is monitored in real time whether the current step has been completed. In the case where it has been completed, the operation type of the next step is determined. If the operation type of the next step is the first operation, the next step is automatically executed. If the operation type of the next step is the second operation, the content of the second operation can be displayed on the terminal, and it is monitored in real time whether the second operation is completed until all operations in the target accident mitigation strategy are completed.

[0120] According to the nuclear power plant accident control method proposed in the embodiments of the present application, by obtaining the operation data of nuclear power equipment within a preset time period, selecting target data that changes over time from the operation data, generating a target sequence of the target data using the target data, identifying whether an accident has occurred based on the target sequence and the operation data to obtain an identification result, in the case where the identification result indicates that an accident has occurred, generating multiple accident mitigation strategies using the operation data and the identification result, performing an index evaluation on the multiple accident mitigation strategies to obtain an index evaluation value, selecting the accident mitigation strategy with the highest index evaluation value from the multiple accident mitigation strategies to obtain a target accident mitigation strategy, inputting the target accident mitigation strategy into a nuclear power accident simulation model for simulation to obtain a simulation result, and in the case where the simulation result meets the preset conditions, executing the target accident mitigation strategy. By generating multiple accident mitigation strategies using the operation data and the identification result, selecting the target accident mitigation strategy with the highest index evaluation value for simulation, and executing the target accident mitigation strategy in the case where the simulation result meets the conditions, it is possible to improve the accuracy and efficiency of the execution of the accident mitigation strategy on the premise of improving the generation efficiency of the accident mitigation strategy.

[0121] Figure 2 is a block diagram of a nuclear power plant accident control device shown according to an exemplary embodiment. Refer to Figure 2 As shown in the figure, the device includes an acquisition unit 201, a first selection unit 202, an identification unit 203, a generation unit 204, an evaluation unit 205, a second selection unit 206, a simulation unit 207, and an execution unit 208.

[0122] Among them, the acquisition unit 201 is configured to acquire the operation data of nuclear power equipment within a preset time period; the preset time period is a time period of a preset duration before the current moment;

[0123] The first selection unit 202 is configured to select target data that changes over time from the operation data, and generate a target sequence of the target data using the target data;

[0124] The identification unit 203 is configured to identify whether an accident has occurred based on the target sequence and the operation data to obtain an identification result;

[0125] The generation unit 204 is configured to generate multiple accident mitigation strategies using the operation data and the identification result in the case where the identification result indicates that an accident has occurred;

[0126] The evaluation unit 205 is configured to perform an index evaluation on the multiple accident mitigation strategies to obtain an index evaluation value;

[0127] The second selection unit 206 is configured to select the accident mitigation strategy with the highest index evaluation value from the multiple accident mitigation strategies to obtain a target accident mitigation strategy;

[0128] The simulation unit 207 is configured to input the target accident mitigation strategy into the nuclear power accident simulation model for simulation to obtain simulation results;

[0129] The execution unit 208 is configured to execute the target accident mitigation strategy when the simulation results meet the preset conditions.

[0130] In some embodiments of the present application, the first selection unit 202 may specifically be configured to:

[0131] Select the pressure data and the core makeup flow rate data of the reactor coolant system within a preset time period from the operation data to obtain target data;

[0132] Generate a first target sequence of the pressure data; the pressure data in the first target data is sorted according to the pressure data acquisition time;

[0133] The identification unit 203 may specifically be configured to:

[0134] Determine the pressure value change rate according to the first target sequence;

[0135] When it is determined that the pressure change amount changes from the first fluctuation state to the second fluctuation state within the preset time period, and the core makeup flow rate starts to decrease from the maximum flow rate value within the preset time period, determine that the core is flooded to obtain an identification result; the first fluctuation state is that the pressure value change rate is greater than or equal to the first change amount; the second fluctuation state is that the pressure value change rate is less than or equal to the second change amount; the first change rate is greater than the second change rate.

[0136] In some embodiments of the present application, the first selection unit 202 may specifically be configured to:

[0137] Obtain the channel information of the containment energy release heat sink within a preset time period from the operation data, and the radiation dose data of the containment within the preset time period;

[0138] Generate a second target sequence of the radiation dose data; the radiation dose data in the second target data is sorted according to the radiation dose data acquisition time;

[0139] The identification unit 203 may specifically be configured to:

[0140] Determine whether there are multiple outliers in the channel information, and determine whether the energy release heat sink can dissipate heat normally according to the operation data;

[0141] Obtain the hydrogen concentration value inside the containment from the operation data, determine whether the hydrogen concentration value inside the containment falls within the preset safety threshold, and determine whether the radiation dose data shows an increasing trend over time according to the second target sequence;

[0142] When there are multiple outliers in the radiation dose data and the energy release heat sink cannot dissipate heat normally, and / or when the hydrogen concentration value in the containment does not fall within the preset safety threshold and the radiation dose data shows a continuous upward trend over time, it is determined that the containment is abnormal, and an identification result is obtained.

[0143] In some embodiments of the present application, the device may further include:

[0144] A display unit for displaying the target accident mitigation strategy on the terminal device;

[0145] A comparison unit for, in response to receiving a modification instruction for the target parameter from the user, comparing the modified value of the target parameter with the preset constraint conditions; the modification instruction includes the modified value;

[0146] A modification unit for, when the modified value meets the preset constraint conditions, modifying the target parameter in the target accident mitigation strategy according to the modification instruction;

[0147] The modification unit is further configured to, in response to identifying a first parameter associated with the target parameter, modify the first parameter according to the preset modification method and the modified value so that the first parameter is adapted to the target parameter.

[0148] In some embodiments of the present application, the execution unit 208 may specifically be configured to:

[0149] Regarding the device in the above embodiments, the specific manner in which each module performs operations has been described in detail in the embodiments related to the method, and will not be elaborated here.

[0150] Determine the operation type of each operation in the target accident mitigation strategy; the operation type includes a first operation and a second operation; the first operation is an operation automatically executed by the computer; the second operation is an operation that requires manual intervention;

[0151] According to the operation execution order in the target accident mitigation strategy, perform the following steps:

[0152] Determine the operation type of the current operation;

[0153] In response to the current operation being the execution of the first operation, control the target device to execute the first operation;

[0154] In response to the currently executed operation being the second operation, monitor whether the user has completed the second operation;

[0155] In the case where it is monitored that the user has completed the second operation, update the next operation to the current operation, and return to execute the step of determining the operation type of the current operation until all operations in the target accident mitigation strategy are completed.

[0156] In some embodiments of the present application, the real-time operation parameters of the unit can be obtained through the data acquisition module, and the valid data among them can be stored in the Redis real-time database. During severe accident conditions, the instrument sensors may encounter conditions beyond their design basis. The system of the present invention does not simply use the method of mutual verification of data validity by multiple groups of instruments, but makes a comparison and correction according to the design basis of the instrument sensors and severe accident conditions. For example, when the water in the containment vessel boils, all the sensors in the containment vessel fail, and subsequent calculations will no longer adopt them; when the spent fuel pool boils, all the sensors in the spent fuel pool space fail, and subsequent calculations will no longer adopt them; when the radiation dose in the steam pipeline exceeds the standard, the instrument values in the steam pipeline obtained will be corrected.

[0157] In some embodiments of the present application, the Web-based front-end user interaction function module can be used as the operation entry for users. When a severe accident is triggered, an accident mitigation measure bar will automatically pop up on the screen, and the user will be guided to jump to the corresponding accident management guidelines.

[0158] In some embodiments of the present application, MySQL relational database can be used for data storage to store business data with low refresh frequency, such as configuration information, user information, unit information, etc. Redis and IOTDB can be used for real-time data storage to store unit data with high change frequency, and provide underlying data support for obtaining parameter trend curves. Relevant auxiliary calculations can be automatically performed according to the obtained instrument parameters, and the corresponding calculation results can be output as trend curves.

[0159] According to the nuclear power plant accident control device proposed in the embodiments of the present application, by obtaining the operation data of nuclear power equipment within a preset time period, selecting target data that changes with time from the operation data, generating a target sequence of the target data using the target data, identifying whether an accident has occurred based on the target sequence and the operation data to obtain an identification result, in the case where the identification result is that an accident has occurred, generating multiple accident mitigation strategies using the operation data and the identification result, performing index evaluation on the multiple accident mitigation strategies to obtain an index evaluation value, selecting the accident mitigation strategy with the highest index evaluation value from the multiple accident mitigation strategies to obtain a target accident mitigation strategy, inputting the target accident mitigation strategy into the nuclear power accident simulation model for simulation to obtain a simulation result, and in the case where the simulation result meets the preset conditions, executing the target accident mitigation strategy. By generating multiple accident mitigation strategies using the operation data and the identification result, selecting the target accident mitigation strategy with the highest index evaluation value for simulation, and executing the target accident mitigation strategy in the case where the simulation result meets the conditions, it is possible to improve the accuracy and efficiency of the execution of the accident mitigation strategy on the premise of improving the generation efficiency of the accident mitigation strategy.

[0160] Figure 3It is a block diagram of a device for a nuclear power plant accident control method shown according to an exemplary embodiment. For example, device 300 may be an electronic device, such as a mobile phone, a computer, a digital broadcast terminal, a messaging device, a game console, a tablet device, a medical device, a fitness device, a personal digital assistant, etc.

[0161] Referring Figure 3 , device 300 may include one or more of the following components: a processing component 302, a memory 304, a power component 306, a multimedia component 308, an audio component 310, an input / output (I / O) interface 312, a sensor component 314, and a communication component 316.

[0162] The processing component 302 generally controls the overall operation of device 300, such as operations associated with display, telephone calls, data communications, camera operations, and recording operations. The processing component 302 may include one or more processors 320 to execute instructions to complete all or part of the steps of the above method. In addition, the processing component 302 may include one or more modules to facilitate the interaction between the processing component 302 and other components. For example, the processing component 302 may include a multimedia module to facilitate the interaction between the multimedia component 308 and the processing component 302.

[0163] The memory 304 is configured to store various types of data to support the operation of device 300. Examples of these data include instructions for any application or method operating on device 300, contact data, phone book data, messages, pictures, videos, etc. The memory 304 may be implemented by any type of volatile or non-volatile storage device or a combination thereof, such as static random access memory (SRAM), electrically erasable programmable read-only memory (EEPROM), erasable programmable read-only memory (EPROM), programmable read-only memory (PROM), read-only memory (ROM), magnetic memory, flash memory, a magnetic disk, or an optical disk.

[0164] The power component 306 provides power to the various components of device 300. The power component 306 may include a power management system, one or more power supplies, and other components associated with generating, managing, and distributing power for device 300.

[0165] The multimedia component 308 includes a screen that provides an output interface between the device 300 and the user. In some embodiments, the screen may include a liquid crystal display (LCD) and a touch panel (TP). If the screen includes a touch panel, the screen can be implemented as a touch screen to receive input signals from the user. The touch panel includes one or more touch sensors to sense touches, swipes, and gestures on the touch panel. The touch sensors can sense not only the boundaries of touch or swipe actions but also detect the duration and pressure associated with the touch or swipe operation. In some embodiments, the multimedia component 308 includes a front camera and / or a rear camera. When the device 300 is in an operating mode, such as a shooting mode or a video mode, the front camera and / or the rear camera can receive external multimedia data. Each of the front camera and the rear camera can be a fixed optical lens system or have a focal length and optical zoom capabilities.

[0166] The audio component 310 is configured to output and / or input audio signals. For example, the audio component 310 includes a microphone (MIC) that is configured to receive external audio signals when the device 300 is in an operating mode, such as a call mode, a recording mode, and a voice recognition mode. The received audio signals can be further stored in the memory 304 or transmitted via the communication component 316. In some embodiments, the audio component 310 further includes a speaker for outputting audio signals.

[0167] The I / O interface 312 provides an interface between the processing component 302 and a peripheral interface module, and the peripheral interface module can be a keyboard, a click wheel, buttons, etc. These buttons can include but are not limited to: a home button, a volume button, a power button, and a lock button.

[0168] The sensor component 314 includes one or more sensors for providing a status assessment of various aspects of the device 300. For example, the sensor component 314 can detect the on / off state of the device 300, the relative positioning of components, such as the display and the keypad of the device 300. The sensor component 314 can also detect a change in the position of the device 300 or a component of the device 300, the presence or absence of user contact with the device 300, the orientation or acceleration / deceleration of the device 300, and the temperature change of the device 300. The sensor component 314 can include a proximity sensor configured to detect the presence of nearby objects without any physical contact. The sensor component 314 can also include a light sensor, such as a CMOS or a CCD image sensor, for use in imaging applications. In some embodiments, the sensor component 314 can further include an acceleration sensor, a gyroscope sensor, a magnetic sensor, a pressure sensor, or a temperature sensor.

[0169] The communication component 316 is configured to facilitate communication between the device 300 and other devices in a wired or wireless manner. The device 300 can access a communication standard-based wireless network, such as WiFi, 2G, or 3G, or a combination thereof. In an exemplary embodiment, the communication component 316 receives a broadcast signal or broadcast-related information from an external broadcast management system via a broadcast channel. In an exemplary embodiment, the communication component 316 further includes a Near Field Communication (NFC) module to facilitate short-range communication. For example, the NFC module can be implemented based on Radio Frequency Identification (RFID) technology, Infrared Data Association (IrDA) technology, Ultra Wideband (UWB) technology, Bluetooth (BT) technology, and other technologies.

[0170] In an exemplary embodiment, the device 300 can be implemented by one or more Application Specific Integrated Circuits (ASICs), Digital Signal Processors (DSPs), Digital Signal Processing Devices (DSPDs), Programmable Logic Devices (PLDs), Field Programmable Gate Arrays (FPGAs), controllers, microcontrollers, microprocessors, or other electronic components for performing the above method.

[0171] In an exemplary embodiment, a non-transitory computer-readable storage medium including instructions is also provided, such as the memory 304 including instructions, and the above instructions can be executed by the processor 320 of the device 300 to complete the above method. For example, the non-transitory computer-readable storage medium can be a ROM, Random Access Memory (RAM), CD-ROM, magnetic tape, floppy disk, and optical data storage device, etc.

[0172] In an exemplary embodiment, a computer program product including a computer program is also provided, and the computer program implements the above method when executed by the processor 320 of the device 300.

[0173] Those skilled in the art will readily conceive of other embodiments of the present invention after considering the specification and practicing the invention disclosed herein. This application is intended to cover any variations, uses, or adaptations of the present invention, which follow the general principles of the present invention and include common general knowledge or conventional technical means in the technical field not disclosed in this disclosure. The specification and embodiments are only regarded as exemplary, and the true scope and spirit of the present invention are pointed out by the following claims.

[0174] It should be understood that the present invention is not limited to the exact structures described above and shown in the drawings, and various modifications and changes can be made without departing from its scope. The scope of the present invention is only limited by the appended claims.

Claims

1. A method for controlling nuclear power plant accidents, characterized in that Including: Obtain the operation data of nuclear power equipment within a preset time period; The preset time period is a time period with a preset duration before the current moment; Select target data that changes with time from the operation data, and generate a target sequence of the target data using the target data; Based on the target sequence and the operation data, identify whether an accident has occurred to obtain an identification result; In the case where the identification result indicates that an accident has occurred, generate multiple accident mitigation strategies using the operation data and the identification result; Conduct index evaluation on the multiple accident mitigation strategies to obtain an index evaluation value; Select the accident mitigation strategy with the highest index evaluation value from the multiple accident mitigation strategies to obtain a target accident mitigation strategy; Input the target accident mitigation strategy into a nuclear power accident simulation model for simulation to obtain a simulation result; In the case where the simulation result meets the preset conditions, execute the target accident mitigation strategy; Wherein, the step of selecting target data that changes with time from the operation data and generating a target sequence of the target data using the target data includes: Select the pressure data and the core makeup flow rate data of the reactor coolant system within the preset time period from the operation data to obtain the target data; Generate a first target sequence of the pressure data; the pressure data in the first target data is sorted according to the pressure data acquisition time; The step of identifying whether an accident has occurred based on the target sequence and the operation data to obtain an identification result includes: Determine the pressure value change rate according to the first target sequence; In the case where it is determined that the pressure change amount changes from a first fluctuation state to a second fluctuation state within the preset time period, and the core makeup flow rate starts to decrease from the maximum flow rate value within the preset time period, determine that the core is flooded to obtain the identification result; the first fluctuation state is that the pressure value change rate is greater than or equal to a first change amount; the second fluctuation state is that the pressure value change rate is less than or equal to a second change amount; the first change rate is greater than the second change rate.

2. The method for controlling nuclear power plant accidents according to claim 1, wherein The step of selecting target data that changes with time from the operation data and generating a target sequence of the target data includes: Obtain the channel information of the containment energy release heat sink within the preset time period from the operation data, and the radiation dose data of the containment within the preset time period; Generate a second target sequence of the radiation dose data; the radiation dose data in the second target data is sorted according to the radiation dose data acquisition time; The step of identifying whether an accident has occurred based on the target sequence and the operation data to obtain an identification result includes: Determine whether there are multiple outliers in the channel information, and determine whether the energy release heat sink can discharge heat normally according to the operation data; Obtain the hydrogen concentration value inside the containment from the operation data, determine whether the hydrogen concentration value inside the containment falls within a preset safety threshold, and determine whether the radiation dose data shows an increasing trend over time according to the second target sequence; When there are multiple outliers in the radiation dose data and the energy release heat sink cannot dissipate heat normally, and / or when the hydrogen concentration value in the containment does not fall within the preset safety threshold and the radiation dose data shows a continuous upward trend over time, it is determined that the containment is abnormal, and the recognition result is obtained.

3. The method for controlling nuclear power plant accidents according to claim 1, characterized in that, After obtaining the target accident mitigation strategy from the accident mitigation strategy with the highest index evaluation value among the multiple accident mitigation strategies, it further includes: Display the target accident mitigation strategy on the terminal device; In response to receiving a modification instruction for the target parameter from the user, compare the modification value of the target parameter with the preset constraint conditions; the modification instruction includes the modification value; When the modification value meets the preset constraint conditions, modify the target parameter in the target accident mitigation strategy according to the modification instruction; In response to recognizing the first parameter associated with the target parameter, modify the first parameter according to the preset modification method and the modification value so that the first parameter is adapted to the target parameter.

4. The method for controlling nuclear power plant accidents according to claim 1, characterized in that, Executing the target accident mitigation strategy includes: Determine the operation type of each operation in the target accident mitigation strategy; the operation type includes a first operation and a second operation; the first operation is an operation automatically executed by the computer; the second operation is an operation that requires manual intervention; Execute the following steps according to the operation execution order in the target accident mitigation strategy: Determine the operation type of the current operation; In response to the current operation being to execute the first operation, control the target device to execute the first operation; In response to the currently executed operation being the second operation, monitor whether the user has completed the second operation; When it is monitored that the user has completed the second operation, update the next operation to the current operation, and return to execute the step of determining the operation type of the current operation until all operations in the target accident mitigation strategy are completed.

5. An accident control device for a nuclear power plant, characterized in that, It includes: An acquisition unit for acquiring the operation data of the nuclear power equipment within a preset time period; The preset time period is a time period with a preset duration before the current moment; A first selection unit for selecting target data that changes over time from the operation data and generating a target sequence of the target data; An identification unit for identifying whether an accident has occurred based on the target sequence and the operation data, and obtaining an identification result; A generation unit for generating multiple accident mitigation strategies using the operation data and the identification result when the identification result is that an accident has occurred; An evaluation unit for evaluating the indexes of the multiple accident mitigation strategies to obtain index evaluation values; A second selection unit for selecting the accident mitigation strategy with the highest index evaluation value from the multiple accident mitigation strategies to obtain the target accident mitigation strategy; A simulation unit for inputting the target accident mitigation strategy into a nuclear power accident simulation model for simulation to obtain a simulation result; An execution unit for executing the target accident mitigation strategy when the simulation result meets the preset conditions; Among them, the first selection unit is specifically used for: Select the pressure data and the core makeup flow rate data of the reactor coolant system during the preset time period from the operating data to obtain the target data; Generate a first target sequence of the pressure data; the pressure data in the first target data is sorted according to the pressure data acquisition time; Identifying whether an accident occurs based on the target sequence and the operating data, the obtained identification result includes: Determine the rate of change of the pressure value according to the first target sequence; When it is determined that the pressure change amount changes from a first fluctuation state to a second fluctuation state during the preset time period, and the core makeup flow rate starts to decrease from the maximum flow rate value during the preset time period, it is determined that the core is flooded to obtain the identification result; the first fluctuation state is that the rate of change of the pressure value is greater than or equal to a first change amount; the second fluctuation state is that the rate of change of the pressure value is less than or equal to a second change amount; the first change rate is greater than the second change rate.

6. An electronic device, characterized in that, Including: A memory, a processor, and a computer program stored on the memory and executable on the processor, when the processor executes the computer program, implementing the method according to any one of claims 1 to 4.

7. A computer-readable storage medium having a computer program stored thereon, characterized in that, When the computer program is executed by the processor, it implements the method according to any one of claims 1 to 4.

8. A computer program product, comprising a computer program, characterized in that, When the computer program is executed by the processor, it implements the method according to any one of claims 1 to 4.

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