Nuclear power plant accident management and control method, device and system

Abstract

The invention relates to a nuclear power plant accident management and control method, device and system. The method comprises the steps of obtaining operation data of nuclear power equipment in a preset time period, selecting target data changing along with time from the operation data, generating a target sequence of the target data by using the target data, identifying whether an accident occurs based on the target sequence and the operation data, and obtaining an identification result, generating a plurality of accident mitigation strategies by using the operation data and the identification result, performing index evaluation on the plurality of accident mitigation strategies to obtain index evaluation values, selecting the accident mitigation strategy with the highest index evaluation value from the plurality of accident mitigation strategies to obtain a target accident mitigation strategy, and inputting the target accident mitigation strategy into the nuclear power accident simulation model for simulation to obtain a simulation result, and executing the target accident mitigation strategy under the condition that the simulation result meets a preset condition. According to the scheme, the accuracy and efficiency of execution of the accident mitigation strategy can be improved.

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 controlling accidents in nuclear power plants. Background Art

[0002] In relevant technologies, a severe accident in a nuclear power plant refers to an accident in which the core of the nuclear power plant reactor is severely damaged and the integrity of the containment is likely to be destroyed, thereby causing environmental radioactive pollution and casualties, resulting in huge losses. Nuclear power plant operators and emergency technical support personnel should quickly formulate appropriate response strategies and accident mitigation measures based on clear action guidelines when a severe accident occurs, so as to reduce the release of radioactive materials, protect the integrity of the containment, and restore the core to a controlled and stable state as much as possible. However, in the practical application of severe accident management in nuclear power plants, most of the mitigation measures are still determined and implemented, resulting in low efficiency and difficulty in timely control of accidents. Summary of the invention

[0003] In order 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 operation 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 with time from the operating data, and using the target data to generate a target sequence of the target data;

[0007] Identify whether an accident occurs based on the target sequence and the operation data, and obtain an identification result;

[0008] In the case where the identification result is an accident, generating a plurality of accident mitigation strategies using the operation 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 index 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 operating data and using the target data to generate a target sequence of the target data includes:

[0014] Selecting the pressure data of the reactor coolant system and the core water replenishment flow data 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] The step of identifying whether an accident occurs based on the target sequence and the operation data to obtain an identification result includes:

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

[0018] When it is determined that the pressure change changes from the first fluctuation state to the second fluctuation state within the preset time period, and the core water replenishment flow rate starts to decrease from the maximum flow value within the preset time period, it is determined that the core is flooded and the identification 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.

[0019] In some embodiments of the present application, the step of selecting target data that varies with time from the operating data and generating a target sequence of target data using the target data includes:

[0020] Acquire channel information of a containment energy release heat sink in the preset time period and radiation dose data of the containment in 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 are sorted according to the radiation dose data acquisition time;

[0022] The step of identifying whether an accident occurs based on the target sequence and the operation data to obtain an identification result includes:

[0023] determining whether there are multiple abnormal values ​​in the channel information, and determining whether the energy release heat sink can discharge heat normally according to the operation data;

[0024] Acquire a hydrogen concentration value in the containment from the operation data, determine whether the hydrogen concentration value in 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;

[0025] When there are multiple abnormal values ​​in the radiation dose data and the energy release heat sink cannot discharge heat normally, and / or when the hydrogen concentration value in the containment does not fall within the preset safety threshold and whether the radiation dose data shows a continuous increasing trend over time, the containment is determined to be abnormal and the identification 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 indicator evaluation value among the multiple accident mitigation strategies, the method further includes:

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

[0028] In response to receiving a modification instruction from a user along with a target parameter, comparing the modified value of the target parameter with a preset constraint condition; the modification instruction includes the modified value;

[0029] In a case where the modified value satisfies the preset constraint condition, modifying the target parameter in the target accident mitigation strategy according to the modification instruction;

[0030] In response to identifying a first parameter associated with the target parameter, the first parameter is modified according to a 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 performed by a computer; the second operation is an operation requiring manual intervention;

[0033] Perform the following steps according to the order of operations in the target incident mitigation strategy:

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

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

[0036] In response to the currently executed operation being the second operation, monitoring whether the user completes the second operation;

[0037] In the case of monitoring that the user completes the second operation, the next operation is updated to the current operation, and the step of determining the operation type of the current operation is returned to be executed until all operations in the target accident mitigation strategy are completed.

[0038] According to a second aspect of an embodiment of the present disclosure, there is provided a nuclear power plant accident control device, comprising:

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

[0040] A first selection unit, 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;

[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 generating unit, configured to generate a plurality of accident mitigation strategies using the operating data and the identification result when the identification result indicates that an accident has occurred;

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

[0044] A second selection unit is used to select the accident mitigation strategy with the highest indicator evaluation value from the multiple accident mitigation strategies to obtain a target accident mitigation strategy;

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

[0046] An execution unit is used to execute the target accident mitigation strategy when the simulation result meets the preset conditions.

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

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

[0049] 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;

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

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

[0052] When it is determined that the pressure change changes from the first fluctuation state to the second fluctuation state within the preset time period, and the core water replenishment flow rate starts to decrease from the maximum flow value within the preset time period, it is determined that the core is flooded and the identification 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 an embodiment of the present disclosure, an electronic device includes: a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein when the processor executes the computer program, the method described in any one of the first aspects is implemented.

[0054] According to a fourth aspect of an embodiment of the present disclosure, there is provided a computer-readable storage medium 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 an embodiment of the present disclosure, a computer program product is provided, comprising a computer program, wherein the computer program implements the method as described in any one of the first aspects when executed by a processor.

[0056] The technical solution provided by the embodiment of the present disclosure may include the following beneficial effects: by obtaining the operation data of the nuclear power equipment within a preset time period, selecting the target data that changes with time from the operation data, generating the target sequence of the target data using the target data, identifying whether an accident occurs based on the target sequence and the operation data, and obtaining the 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, obtaining the index evaluation value, selecting the accident mitigation strategy with the highest index evaluation value from the multiple accident mitigation strategies, obtaining the target accident mitigation strategy, inputting the target accident mitigation strategy into the nuclear power accident simulation model for simulation, obtaining the 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, the accuracy and efficiency of the execution of the accident mitigation strategy can be improved under the premise of improving the efficiency of the generation of the accident mitigation strategy.

[0057] It is to be understood that the foregoing general description and the following detailed description are exemplary and explanatory only and are not restrictive of the present disclosure. BRIEF DESCRIPTION OF THE DRAWINGS

[0058] The accompanying drawings, which are incorporated in and constitute a part of this specification, illustrate embodiments consistent with the invention and, together with the description, serve to explain the principles of the invention.

[0059] Figure 1 The present invention is a flowchart of a method for accident management and control of a nuclear power plant according to an exemplary embodiment.

[0060] Figure 2 It is a block diagram of a nuclear power plant accident management and control device according to an exemplary embodiment.

[0061] Figure 3 It is a block diagram of a device for a nuclear power plant accident management method according to an exemplary embodiment. DETAILED DESCRIPTION

[0062] Exemplary embodiments will be described in detail herein, examples of which are shown in the accompanying drawings. When the following description refers to the drawings, the same numbers in different drawings represent the same or similar elements unless otherwise indicated. The embodiments described in the following exemplary embodiments do not represent all embodiments consistent with the present invention. Instead, 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 disclosed embodiments are only for the purpose of describing specific embodiments, and are not intended to limit the disclosed embodiments. The singular forms "a", "an" and "the" used in the disclosed embodiments and the appended claims are also intended to include plural forms, unless the context clearly indicates other meanings.

[0064] It should be understood that although the terms first, second, third, etc. may be used to describe various information in the disclosed embodiments, 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 disclosed embodiments, 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 "if" as used herein may be interpreted as "at" or "when" or "in response to determination".

[0065] In addition, various forms of processes shown in the embodiments of the present disclosure may be used to reorder, add or delete steps. For example, the steps described in the present application may be performed in parallel, sequentially or in different orders, as long as the desired results of the technical solution disclosed in the present application can be achieved, and this document does not limit this.

[0066] In the relevant technology, a serious accident in a nuclear power plant refers to an accident in which the reactor core of a nuclear power plant is seriously damaged and may damage the integrity of the containment, thereby causing environmental radioactive pollution and personal injury, resulting in huge losses. Operators and emergency technical support personnel of nuclear power plants should, in the event of a serious accident, quickly formulate appropriate response strategies and accident mitigation measures based on clear action guidelines to reduce the release of radioactive materials, protect the integrity of the containment, and restore the core to a controlled and stable state as much as possible. A serious accident in a nuclear power plant refers to an accident in which the reactor core of a nuclear power plant is seriously damaged and may damage the integrity of the containment, thereby causing environmental radioactive pollution and personal injury, resulting in huge losses. Operators and emergency technical support personnel of nuclear power plants should, in the event of a serious accident, quickly formulate appropriate response strategies and accident mitigation measures based on clear action guidelines to reduce the release of radioactive materials, protect the integrity of the containment, and restore the core to a controlled and stable state as much as possible. However, in the practical application of severe accident management in nuclear power plants, most of the mitigation measures are still determined and implemented, resulting in low efficiency and difficulty in timely control of accidents.

[0067] In order to solve the above problems, the present disclosure provides a nuclear power plant accident control method, device and system, which obtains the operation data of nuclear power equipment within a preset time period, selects target data that changes with time from the operation data, generates a target sequence of target data using the target data, identifies whether an accident occurs based on the target sequence and the operation data, and obtains an identification result. When the identification result is that an accident occurs, multiple accident mitigation strategies are generated using the operation data and the identification result, and index evaluation is performed on multiple accident mitigation strategies to obtain an index evaluation value. The accident mitigation strategy with the highest index evaluation value is selected from multiple accident mitigation strategies to obtain a target accident mitigation strategy, and the target accident mitigation strategy is input into a nuclear power accident simulation model for simulation to obtain a simulation result. When the simulation result meets the preset conditions, the target accident mitigation strategy is executed. 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, the accuracy and efficiency of the execution of the accident mitigation strategy can be improved under the premise of improving the generation efficiency of the accident mitigation strategy.

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

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

[0070] The preset time period is a time period of preset duration before the current moment.

[0071] It should be noted that in order to more accurately identify whether an accident has occurred, it is not only necessary to identify based on the operating data collected at the current moment, but also necessary to evaluate the data in a period of time before the current time node as a whole, so as to identify the changes in data over a period of time, thereby improving the accuracy of identifying accidents.

[0072] Step 102, selecting target data that changes with time from the operating data, and using the target data to generate a target sequence of the target data.

[0073] In one embodiment, data whose values ​​change over time may be selected from the operating data as target data, and a target sequence may be generated using the target data.

[0074] In one embodiment, the target data in the target sequence may be sorted according to the time when the data was collected.

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

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

[0077] Step 103 may specifically include: determining 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 a preset time period, and the core water replenishment flow rate starts to decrease from the maximum flow value within the preset time period, determining that the core is flooded and obtaining an identification 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 based on the relationship between the pressure change trend of the reactor coolant system and the core water replenishment flow rate. When the coolant pressure changes from violent fluctuations (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 water replenishment flow rate gradually decreases from the maximum flow rate, the occurrence of core flooding can be determined, which is more accurate than simply relying on the value of the water level sensor in the containment to determine whether the core is flooded.

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

[0081] Obtaining channel information of the containment energy release heat sink in a preset time period and radiation dose data of the containment in the preset time period from the operation data;

[0082] generating a second target sequence of 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 abnormal values ​​in the channel information, and determine whether the energy release heat sink can discharge heat normally based on the operating data;

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

[0086] When there are multiple abnormal values ​​in the radiation dose data and the energy release heat sink cannot discharge heat normally, and / or when the hydrogen concentration value in the containment does not fall within the preset safety threshold and whether the radiation dose data shows a continuous increasing trend over time, the containment is determined to be abnormal and an identification result is obtained.

[0087] In the embodiment of the present application, whether the energy release heat sink can dissipate heat normally can be determined by running data to find out whether the heat dissipation rate of the energy release heat sink meets the standard.

[0088] In one embodiment, it can be determined whether the data of the containment energy release heat sink channel is continuously abnormal and cannot discharge heat normally, or whether the hydrogen concentration in the containment exceeds the safety range and the radiation dose level in the containment continues to increase significantly. In the case where there are multiple abnormal values ​​in the radiation dose data and the energy release heat sink cannot discharge 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 trend of continuous increase over time, the containment is determined to be abnormal.

[0089] In some embodiments of the present application, the core injection system flow rate and the total water loading of the heat release loop in the reactor can also be obtained from the operation data. When the core injection system flow rate is continuously lower than the low flow setting value F, and the total water loading of the first loop is less than the low water loading setting value M, it can be determined that the core has entered the exposed state, without waiting until the core temperature reaches 650 degrees Celsius or the fuel rod cladding temperature reaches 800 degrees Celsius to determine that the core has entered the exposed state. The low flow setting value F of the injection system is linearly inversely proportional to the three-dimensional total water loading value M of the heat release loop in the reactor. 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 channel for energy release in the containment is available, and the sensor data in the heat sink channel is valid and has no abnormalities; 2. The containment boundary is physically intact, and the containment boundary pressure has no abnormalities; 3. The hydrogen concentration in the containment is within a safe range and has not reached a combustible concentration; if all three of the above conditions are met, it can be determined that the containment is intact and controllable without relying 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 required decay heat removal and in combination with the current operating conditions. When there is no breach in the heat release circuit 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 demand, the containment pit recirculation water injection method and the steam generator secondary side water injection method are automatically superimposed and opened without manual intervention. If there is a breach in the heat release circuit in the reactor, the containment pit recirculation water injection method is directly used. If this method is still insufficient to remove the decay heat, the steam generator secondary side water injection method can also be automatically superimposed as a supplementary method.

[0092] Step 103, identifying whether an accident occurs based on the target sequence and the operation data, and obtaining an identification result.

[0093] Step 104 , when the identification result indicates that an accident has occurred, multiple accident mitigation strategies are generated using the operating data and the identification result.

[0094] Step 105: perform index evaluation on multiple accident mitigation strategies to obtain index evaluation values.

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

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

[0097] It is understandable that in order to find a better accident mitigation strategy, multiple feasible accident mitigation strategies can be generated, and the multiple accident mitigation strategies can be 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] Displaying the target incident mitigation strategy on the terminal device;

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

[0101] When the modified value satisfies the preset constraint condition, modifying the target parameter in the target accident mitigation strategy according to the modification instruction;

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

[0103] In an 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 the terminal device so that the user can review and adjust the target accident mitigation strategy.

[0104] In one embodiment, after receiving the user's indication of modification of the target parameter, the modified value of the target parameter can be compared with the preset constraint condition, that is, to determine whether the modified value input by the user meets the requirement, so as to avoid problems in the target accident mitigation strategy after modification due to the user input data not meeting the requirement.

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

[0106] It should be noted that the above constraint conditions may be preset according to the characteristics of the above target parameters and actual requirements. The constraint conditions may be used to control the modified value within a reasonable range.

[0107] It is understandable that in the case of a nuclear power accident, time is very precious. The earlier the accident mitigation strategy is implemented, the more the loss caused by the accident can be reduced. Therefore, in a more urgent situation, the first parameter associated with the above-mentioned target parameter can be identified, and the first parameter can be modified according to the preset modification method and modification value to make the first parameter compatible with the target parameter. In this way, the target accident mitigation strategy can be quickly modified in an emergency, which improves the efficiency and accuracy of parameter modification compared to relying on manual modification of all parameters, thereby improving the speed of executing the accident mitigation strategy.

[0108] Step 107, inputting the target accident mitigation strategy into the nuclear power accident simulation model for simulation to obtain simulation results.

[0109] Step 108, when the simulation results meet the preset conditions, execute the target accident mitigation strategy.

[0110] It is understandable 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 results meet 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 performed by a computer; the second operation is an operation requiring manual intervention;

[0113] Perform the following steps according to the order of actions in the target incident mitigation strategy:

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

[0115] In response to the current operation being to execute a first operation, controlling the target device to execute the first operation;

[0116] In response to the currently executed operation being the second operation, monitoring whether the user completes the second operation;

[0117] When it is monitored that the user completes the second operation, the next operation is updated to the current operation, and the step of determining the operation type of the current operation is returned to be executed until all operations in the target accident mitigation strategy are completed.

[0118] It is understandable that since the target accident mitigation strategy may contain both operations performed automatically by the computer and operations requiring human intervention, the operations performed by the computer are controllable, while the operations requiring human intervention have uncontrollable factors. Therefore, in order to improve 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, in 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 manually intervened operation, it is monitored in real time whether the current step has been completed. If 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 the completion of the second operation can be monitored in real time until all operations in the target accident mitigation strategy are completed.

[0120] According to the nuclear power plant accident control method proposed in the embodiment of the present application, by obtaining the operating data of the nuclear power equipment within a preset time period, selecting the target data that changes with time from the operating data, using the target data to generate a target sequence of the target data, identifying whether an accident occurs based on the target sequence and the operating data, and obtaining an identification result, when the identification result is that an accident occurs, using the operating data and the identification result to generate multiple accident mitigation strategies, performing index evaluation on the multiple accident mitigation strategies, obtaining an index evaluation value, selecting the accident mitigation strategy with the highest index evaluation value from the multiple accident mitigation strategies, obtaining a target accident mitigation strategy, inputting the target accident mitigation strategy into the nuclear power accident simulation model for simulation, obtaining 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 operating 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, the accuracy and efficiency of the execution of the accident mitigation strategy can be improved under the premise of improving the efficiency of the generation of the accident mitigation strategy.

[0121] Figure 2 FIG. 1 is a block diagram of a nuclear power plant accident control device according to an exemplary embodiment. Figure 2 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] The acquisition unit 201 is used to acquire the operation data of the nuclear power equipment within a preset time period; the preset time period is a time period of a preset length before the current moment;

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

[0124] An identification unit 203 is used to identify whether an accident occurs based on the target sequence and the operation data, and obtain an identification result;

[0125] A generating unit 204, configured to generate a plurality of accident mitigation strategies using the operation data and the identification result when the identification result indicates that an accident has occurred;

[0126] An evaluation unit 205, configured to perform an index evaluation on a plurality of accident mitigation strategies to obtain an index evaluation value;

[0127] A second selection unit 206 is used to select an accident mitigation strategy with the highest indicator evaluation value from multiple accident mitigation strategies to obtain a target accident mitigation strategy;

[0128] The simulation unit 207 is used 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 used to execute the target accident mitigation strategy when the simulation result meets the preset conditions.

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

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

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

[0133] The identification unit 203 may be specifically used for:

[0134] determining a pressure value change rate according to a first target sequence;

[0135] When it is determined that the pressure change changes from the first fluctuation state to the second fluctuation state within the preset time period, and the core water replenishment flow rate starts to decrease from the maximum flow value within the preset time period, it is determined that the core is flooded and an identification 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.

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

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

[0138] generating a second target sequence of 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 be specifically used for:

[0140] Determine whether there are multiple abnormal values ​​in the channel information, and determine whether the energy release heat sink can discharge heat normally based on the operating data;

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

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

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

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

[0145] A comparison unit, configured to compare the modified value of the target parameter with the preset constraint condition in response to receiving a modification instruction from a user along with the target parameter; the modification instruction includes the modified value;

[0146] a modification unit, configured to modify a target parameter in a target accident mitigation strategy according to a modification instruction if the modification value satisfies a preset constraint condition;

[0147] The modification unit is further used to modify the first parameter in response to identifying the first parameter associated with the target parameter according to a preset modification method and modification 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 be specifically used to:

[0149] Regarding the device in the above embodiment, the specific manner in which each module performs operations has been described in detail in the embodiment of 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 performed by a computer; the second operation is an operation requiring manual intervention;

[0151] Perform the following steps according to the order of actions in the target incident mitigation strategy:

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

[0153] In response to the current operation being to execute a first operation, controlling the target device to execute the first operation;

[0154] In response to the currently executed operation being the second operation, monitoring whether the user completes the second operation;

[0155] When it is monitored that the user completes the second operation, the next operation is updated to the current operation, and the step of determining the operation type of the current operation is returned to be executed until all operations in the target accident mitigation strategy are completed.

[0156] In some embodiments of the present application, the real-time operating parameters of the unit can be obtained through the data acquisition module, and the valid data therein can be stored in the Redis real-time database. During severe accident conditions, instrument sensors may be subjected to conditions that exceed their design benchmarks. The system of the present invention does not simply adopt a method of multiple groups of instruments to verify the validity of data with each other, but makes comparative corrections according to the design benchmark of the instrument sensor and severe accident conditions. For example: when the water in the containment boils, all sensors in the containment fail, and subsequent calculations are no longer used; when the fuel spent pool boils, all sensors in the spent pool space fail, and subsequent calculations are no longer used; when the radiation dose in the steam pipeline exceeds the standard, the instrument values ​​obtained in the steam pipeline are corrected.

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

[0158] In some embodiments of the present application, data storage can use MySQL relational database to store business data with low refresh frequency, such as configuration information, user information, unit information, etc. Real-time data storage can use Redis and IOTDB to store unit data with high change frequency, and provide underlying data support for parameter trend curve acquisition. Relevant auxiliary calculations can be automatically performed according to the acquired 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 embodiment of the present application, by obtaining the operating data of the nuclear power equipment within a preset time period, selecting the target data that changes with time from the operating data, using the target data to generate a target sequence of the target data, identifying whether an accident occurs based on the target sequence and the operating data, and obtaining an identification result, when the identification result is that an accident occurs, using the operating data and the identification result to generate multiple accident mitigation strategies, performing index evaluation on the multiple accident mitigation strategies, obtaining an index evaluation value, selecting the accident mitigation strategy with the highest index evaluation value from the multiple accident mitigation strategies, obtaining a target accident mitigation strategy, inputting the target accident mitigation strategy into the nuclear power accident simulation model for simulation, obtaining 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 operating 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, the accuracy and efficiency of the execution of the accident mitigation strategy can be improved under the premise of improving the efficiency of the generation of the accident mitigation strategy.

[0160] Figure 3300 is a block diagram of a device for a nuclear power plant accident management method according to an exemplary embodiment. For example, the device 300 may be an electronic device, such as a mobile phone, a computer, a digital broadcast terminal, a message transceiver device, a game console, a tablet device, a medical device, a fitness device, a personal digital assistant, etc.

[0161] Reference Figure 3 , the 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 the device 300, such as operations associated with display, phone 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-mentioned 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 operations on the device 300. Examples of such data include instructions for any application or method operating on the device 300, contact data, phone book data, messages, pictures, videos, etc. The memory 304 can 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, magnetic disk or optical disk.

[0164] The power component 306 provides power to the various components of the 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 the 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 may be implemented as a touch screen to receive input signals from the user. The touch panel includes one or more touch sensors to sense touch, slide, and gestures on the touch panel. The touch sensor may not only sense the boundaries of the touch or slide action, but also detect the duration and pressure associated with the touch or slide 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 may receive external multimedia data. Each front camera and rear camera may be a fixed optical lens system or have a focal length and optical zoom capability.

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

[0167] I / O interface 312 provides an interface between processing component 302 and peripheral interface modules, such as keyboards, click wheels, buttons, etc. These buttons may include but are not limited to: a home button, a volume button, a start button, and a lock button.

[0168] The sensor assembly 314 includes one or more sensors for providing various aspects of status assessment for the device 300. For example, the sensor assembly 314 can detect the open / closed state of the device 300, the relative positioning of components, such as the display and keypad of the device 300, the sensor assembly 314 can also detect the position change 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 assembly 314 may include a proximity sensor configured to detect the presence of nearby objects without any physical contact. The sensor assembly 314 may also include an optical sensor, such as a CMOS or CCD image sensor, for use in imaging applications. In some embodiments, the sensor assembly 314 may also include an accelerometer, a gyroscope sensor, a magnetic sensor, a pressure sensor, or a temperature sensor.

[0169] The communication component 316 is configured to facilitate wired or wireless communication between the device 300 and other devices. The device 300 can access a wireless network based on a communication standard, 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 also 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 apparatus 300 may 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 to perform the above method.

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

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

[0173] Those skilled in the art will readily appreciate 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 that follow the general principles of the present invention and include common knowledge or customary techniques in the art that are not disclosed in this disclosure. The specification and examples are to be considered exemplary only, and the true scope and spirit of the present invention are indicated by the following claims.

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

Claims

1. A method for controlling an accident in a nuclear power plant, characterized in that: include: Obtaining the operating data of nuclear power equipment within a preset time period; The preset time period is a time period of preset duration before the current moment; Selecting target data that changes with time from the operating data, and using the target data to generate a target sequence of the target data; Identify whether an accident occurs based on the target sequence and the operation data, and obtain an identification result; In the case where the identification result is an accident, generating a plurality of 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 simulation results; When the simulation result meets the preset conditions, the target accident mitigation strategy is executed.

2. The nuclear power plant accident management method according to claim 1, characterized in that: The step of selecting target data that changes over time from the operating data and using the target data to generate a target sequence of the target data includes: Selecting the pressure data of the reactor coolant system and the core water replenishment flow data within the preset time period from the operation data to obtain the target data; 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; The step of identifying whether an accident occurs based on the target sequence and the operation data to obtain an identification result includes: determining a pressure value change rate according to the first target sequence; When it is determined that the pressure change changes from the first fluctuation state to the second fluctuation state within the preset time period, and the core water replenishment flow rate starts to decrease from the maximum flow value within the preset time period, it is determined that the core is flooded and the identification 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.

3. The nuclear power plant accident management and control method according to claim 1, characterized in that: The step of selecting target data that changes over time from the operating data and using the target data to generate a target sequence of target data includes: Acquire channel information of a containment energy release heat sink in the preset time period and radiation dose data of the containment in the preset time period from the operation data; generating a second target sequence of the radiation dose data; the radiation dose data in the second target data are sorted according to the radiation dose data acquisition time; The step of identifying whether an accident occurs based on the target sequence and the operation data to obtain an identification result includes: determining whether there are multiple abnormal values ​​in the channel information, and determining whether the energy release heat sink can discharge heat normally according to the operation data; Acquire a hydrogen concentration value in the containment from the operation data, determine whether the hydrogen concentration value in 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 abnormal values ​​in the radiation dose data and the energy release heat sink cannot discharge heat normally, and / or when the hydrogen concentration value in the containment does not fall within the preset safety threshold and whether the radiation dose data shows a continuous increasing trend over time, the containment is determined to be abnormal and the identification result is obtained.

4. The nuclear power plant accident management method according to claim 1, characterized in that: After obtaining the target accident mitigation strategy from the accident mitigation strategy with the highest indicator evaluation value among the multiple accident mitigation strategies, the method further includes: Displaying the target accident mitigation strategy on a terminal device; In response to receiving a modification instruction from a user along with a target parameter, comparing the modified value of the target parameter with a preset constraint condition; the modification instruction includes the modified value; In a case where the modified value satisfies the preset constraint condition, modifying the target parameter in the target accident mitigation strategy according to the modification instruction; In response to identifying a first parameter associated with the target parameter, the first parameter is modified according to a preset modification method and the modification value so that the first parameter is adapted to the target parameter.

5. The nuclear power plant accident management method according to claim 1, characterized in that: The 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 performed by a computer; the second operation is an operation requiring manual intervention; Perform the following steps according to the order of operations in the target incident mitigation strategy: Determine the operation type of the current operation; In response to the current operation being to execute the first operation, controlling the target device to execute the first operation; In response to the currently executed operation being the second operation, monitoring whether the user completes the second operation; In the case of monitoring that the user completes the second operation, the next operation is updated to the current operation, and the step of determining the operation type of the current operation is returned to be executed until all operations in the target accident mitigation strategy are completed.

6. A nuclear power plant accident control device, characterized in that: include: An acquisition unit, used to acquire operation data of nuclear power equipment within a preset time period; The preset time period is a time period of preset duration before the current moment; A first selection unit, 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; an identification unit, configured to identify whether an accident occurs based on the target sequence and the operation data, and obtain an identification result; a generating unit, configured to generate a plurality of accident mitigation strategies using the operating data and the identification result when the identification result indicates that an accident has occurred; An evaluation unit, configured to perform an index evaluation on the plurality of accident mitigation strategies to obtain an index evaluation value; A second selection unit is used to select the accident mitigation strategy with the highest indicator evaluation value from the multiple accident mitigation strategies to obtain a target accident mitigation strategy; A simulation unit, used for inputting the target accident mitigation strategy into a nuclear power accident simulation model for simulation to obtain a simulation result; An execution unit is used to execute the target accident mitigation strategy when the simulation result meets the preset conditions.

7. The nuclear power plant accident control device according to claim 2, characterized in that: The first selection unit is specifically used for: Selecting the pressure data of the reactor coolant system and the core water replenishment flow data within the preset time period from the operation data to obtain the target data; generating a first target sequence of pressure data; The pressure data in the first target data are sorted according to the pressure data collection time; The step of identifying whether an accident occurs based on the target sequence and the operation data to obtain an identification result includes: determining a pressure value change rate according to the first target sequence; When it is determined that the pressure change changes from the first fluctuation state to the second fluctuation state within the preset time period, and the core water replenishment flow rate starts to decrease from the maximum flow value within the preset time period, it is determined that the core is flooded and the identification 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.

8. An electronic device, characterized in that: include: A memory, a processor, and a computer program stored in the memory and executable on the processor, wherein when the processor executes the computer program, the method according to any one of claims 1 to 5 is implemented.

9. A computer-readable storage medium having a computer program stored thereon, characterized in that: When the computer program is executed by a processor, the method according to any one of claims 1 to 5 is implemented.

10. A computer program product, comprising a computer program, characterized in that The computer program implements the method according to any one of claims 1 to 5 when executed by a processor.

Images