Serious accident simulation data driving method and device for external nuclear power plant

Abstract

The invention provides an external nuclear power plant serious accident simulation data driving method and device, and the method comprises the steps: carrying out the real-time analysis and processing of the real-time parameter data obtained through the calculation of a data obtaining module through the real-time calculation of the thermal parameters, electrical performance parameters, reactor core parameters and instrument control parameters of a nuclear power plant system; comprising the steps of data compensation calculation, abnormal signal detection and state mode recognition, so that thermotechnical data needed for triggering a serious accident changes stably, and data step changes or oscillation changes do not exist; and the processed data is transmitted to a serious accident simulation system of a technical support center, and a data source is provided for subsequent simulation calculation of a serious accident simulator. According to the invention, on the premise that a full-range simulator system is not transformed, simulation data required for triggering severe accident simulation can be obtained only by relying on one host, that is, the severe accident simulator can complete initialization starting according to the data provided by the driver.

Description

Technical Field

[0001] The present application relates to the field of data processing technology, and in particular to an external nuclear power plant severe accident simulation data driving method, device, electronic equipment and storage medium. Background Art

[0002] With the popularization of nuclear energy utilization, the number of nuclear power plants is also increasing. However, various accidents may occur during the operation of nuclear power plants, among which severe accidents will have a significant impact on personnel, environment and equipment. Therefore, for the technical support center of nuclear power plants, how to conveniently and efficiently obtain and process severe accident data in order to simulate severe accidents is an important issue facing current technology.

[0003] The existing severe accident simulation mainly relies on the transformation of the traditional full-range simulator, and the relevant software and hardware required for triggering severe accident simulation calculations are built into the full-range simulator, so that the simulation data required for triggering severe accident simulation can be obtained through the full-range simulator system. On the one hand, the full-range simulator system is mainly used for routine operation training and examination of nuclear power plant operators. When the full-range simulator system is used to obtain the simulation data required for triggering severe accident simulation, it cannot be used for routine operation training, and when the full-range simulator system is used for routine operation training, it cannot be used to obtain the simulation data required for triggering severe accident simulation. On the other hand, the full-range simulator system is usually composed of thirty or forty hosts and more than eighty related systems. When used to obtain the simulation data required for triggering severe accident simulation, only a few dozen systems are in working state, and the other sixty or seventy systems are in dormant state, which causes great waste of system resources. The smooth transition algorithm calculation of the present invention only needs one host to obtain the simulation data required for triggering severe accident simulation, and no longer needs to rely on the transformation of the full-range simulator to obtain the simulation data required for triggering severe accident simulation. In addition, improper processing of the data triggering severe accidents calculated by the full-range simulator can easily lead to disturbances and uneven changes in the values ​​of key parameters, affecting the accuracy of the calculation results and hindering the analysis of severe accident phenomena. Summary of the invention

[0004] The present application aims to solve one of the technical problems in the related art at least to some extent.

[0005] To this end, the first purpose of the present application is to propose an external nuclear power plant severe accident simulation data driving method, which aims to obtain the simulation data required to trigger severe accident simulation without modifying the full-range simulator system, relying only on one host, that is, the severe accident simulator can complete the initialization startup according to the data provided by this driver.

[0006] The second objective of the present application is to provide an external nuclear power plant severe accident simulation data driving device.

[0007] The third objective of the present application is to provide an electronic device.

[0008] A fourth objective of the present application is to provide a computer-readable storage medium.

[0009] To achieve the above-mentioned purpose, the first embodiment of the present application proposes an external nuclear power plant severe accident simulation data-driven method, comprising:

[0010] Acquire nuclear power plant severe accident simulation data in real time from the nuclear power plant database;

[0011] Analyze and process the severe accident simulation data of nuclear power plants to ensure that the severe accident simulation data required to trigger severe accidents changes smoothly;

[0012] The analyzed and processed nuclear power plant severe accident simulation data is transmitted to the severe accident simulation system of the nuclear power plant technical support center to provide a data source for subsequent severe accident simulator simulation calculations.

[0013] Among them, the severe accident simulation data of nuclear power plants include thermal parameters, electrical performance parameters, core parameters and instrumentation and control parameters;

[0014] The thermal parameters are obtained by modeling the thermal parameters related systems of the primary and secondary loop systems of the nuclear power plant with high precision through thermal flow network modeling and then through model simulation; the thermal parameters at least include the reactor core temperature, the pressurizer pressure and the steam flow of the steam generator;

[0015] The electrical performance parameters are obtained by model simulation after high-precision electrical network modeling of the power supply system of the nuclear power plant; the electrical performance parameters include at least the current, voltage, active power and reactive power of the main generator and the standby generator, the current, voltage, active power and reactive power of the reactor coolant main pump, and the current, voltage, active power and reactive power of the main feed water system;

[0016] The core parameters are obtained by model simulation after high-precision reactor core dynamics modeling of the nuclear power plant reactor main system; the core parameters at least include reactor neutron flux, decay heat and radioactive source terms;

[0017] The instrumentation and control parameters are obtained through model simulation after high-precision control logic modeling and human-machine operation screen modeling of the systems involved in the thermal, electrical and core models of the nuclear power plant; the control parameters at least include the logical operation parameters of the DCS control system.

[0018] Among them, the analysis and processing of severe accident simulation data of nuclear power plants include:

[0019] Data recognition is performed on the severe accident simulation data of nuclear power plants. According to whether the change of the calculation results of the parameters in the process of triggering severe accidents is stable without step oscillation, the severe accident simulation data of nuclear power plants are divided into calculation processing parameters and specific processing parameters;

[0020] For the calculation and processing parameters, a smooth transition algorithm is used for processing;

[0021] For specific processing parameters, specific processing is performed according to the data type.

[0022] Among them, the types of calculated processing parameters include: the mass, energy, temperature, pressure, cavitation fraction and water level of each control body node or equipment in the nuclear power plant; the fluid flow rate of each connection node, including liquid, steam and non-condensable gas; the temperature of each thermal component node, including the fuel element node temperature, cladding temperature, control rod node temperature, as well as the wall temperature of the pressure vessel, pressurizer, main pipeline, and the containment thermal component and shell wall temperature.

[0023] Among them, the smooth transition algorithm formula used for calculating processing parameters is expressed as:

[0024]

[0025] Among them, X d is the calculation processing parameter, X dis Smooth transition algorithm calculation, X m is the value calculated by the severe accident program, t s is the time to trigger a severe accident, Δt r is the transition period, and t is the current operation time.

[0026] Among them, for specific processing parameters, specific processing is performed according to the data type, including:

[0027] The specific processing parameter is the severe accident simulation calculation time. When a severe accident is triggered, the current time is transmitted to the start time of the severe accident simulator. If the reactor is shut down or the reactor coolant main pump trips before the severe accident is triggered, the corresponding severe accident event mark is set according to the data transmitted from the smooth transition algorithm and the time of the reactor shutdown or the reactor coolant main pump trip is recorded. The attenuation power is calculated according to the difference between the time of triggering the severe accident and the time of the reactor shutdown or the pump trip.

[0028] The specific processing parameters are the physical properties of the system nodes. The mass and energy of the node are calculated based on the water and gas temperature, pressure and average cavitation fraction data in each system node. If the cavitation fraction is less than 1.0*e -6, the node is assumed to be a water entity; if the cavitation fraction is greater than 0.999999, the node is assumed to be filled with superheated steam; if the void fraction is 1.0*e -6 and 0.999999, the node is assumed to be filled with a two-phase mixture of steam and water; if the temperature difference between water and steam is less than 1.0K, and the void fraction is less than 0.6, the water and steam phases are assumed to be in thermal equilibrium;

[0029] The specific processing parameters are the pressurizer gas-liquid state, the water level in the pressurizer is used as input, and the conditions of "water entity" condition or "steam fill" condition are determined based on the collapsed water level;

[0030] The specific processing parameter is the water level on the secondary side of the steam generator. The input of the secondary side conditions of the steam generator includes pressure, collapse water level in the downcomer, and water and gas temperature. The thermal hydraulic model of the steam generator is a dual-zone model, in which the area in contact with the tube bundle and the steam-water separator is set as zone 1, and the downcomer and the dome are set as zone 2. Based on the collapse water level in the downcomer, the water and gas space properties in zone 2 are calculated, and the collapse water level in zone 1 is set to be the same as the collapse water level in zone 2. This assumption of the same water level is applicable to the case where there is no obvious heat transfer from the primary side to the secondary side, and there is no obvious discharge from the steam generator.

[0031] The specific processing parameters are the water-gas properties in the pressure relief tank, which are calculated based on the water and gas temperature, pressure and cavitation fraction in the pressure relief tank; if the bursting disk is intact, the pressure relief tank is assumed to be filled with uniformly mixed water and steam; if the bursting disk is ruptured, it is assumed that the liquid phase and the gas phase are separated, and the hypothetical pressure relief tank is filled with water, steam and air;

[0032] The specific treatment parameters are the reactor coolant system heat sink temperature. The reactor coolant system heat sink includes the reactor vessel wall, cold leg and hot leg walls, and steam generator heat transfer tubes. Except for the steam generator heat transfer tubes, the temperature of the heat sink does not need to be provided. Instead, it is assumed that:

[0033] If the inner and / or outer surfaces of the heat sink are in contact with a reactor coolant system node, the surface temperature is very close to the reactor coolant system water or gas temperature, depending on whether the heat sink surface is covered by water or gas;

[0034] If the inner or outer surface of the heat sink is in contact with the containment node, the heat transfer coefficient h between the heat sink and the containment node is c The heat sink temperature T is calculated from the heat loss from the reactor coolant system to the containment under steady-state conditions. o The energy balance based on the surface is given by:

[0035]

[0036] Among them, k S is the thermal conductivity of the heat sink, Δx s is the thickness of the heat sink, T i is the temperature on the other side of the heat sink in contact with the reactor coolant system node, T o is the water or gas temperature in the containment node;

[0037] For the steam generator heat transfer tube, the temperature distribution on the heat sink thickness is assumed to be a linear function, and the inner and outer surface temperatures calculated by the smooth transition algorithm are used as input;

[0038] The specific processing parameters are the fuel and cladding temperatures, and the calculation of the heat transfer coefficient from the cladding to the water before calculating the fuel and cladding temperatures and energies at the time of triggering a severe accident;

[0039] If the reactor coolant main pump is in operation or has tripped before a severe accident is triggered, the flow rate through the core is calculated from the reactor coolant main pump curve or the fallback curve;

[0040] The heat transfer coefficient is calculated based on the forced circulation relationship. If the trip time of the reactor coolant main pump exceeds the preset time, the heat transfer coefficient is 100W / ㎡·℃, and the decay power at the time of switching is used to calculate the heat flux density from the cladding to the water. The temperature of the cladding and fuel is determined by the energy balance relationship from the fuel center to the water.

[0041] The specific processing parameters are the mass and energy of water and gas in the containment node, using the total pressure, partial pressures of steam, water and gas temperature, and the collapsed water level in the containment node as input; the water and gas in the containment are assumed to be separate and have their own specific temperatures, and the volume occupied by water and gas is calculated based on the water level in the containment node; the mass and energy of water are calculated based on the water temperature and the total pressure; the gas in the containment node is assumed to be a mixture of steam and air, the steam partial pressure is provided by the smoothing algorithm, and the air partial pressure is calculated from the difference between the total pressure and the steam partial pressure, and the gas mass and energy are calculated based on the partial pressure and the gas temperature;

[0042] The specific treatment parameter is the temperature of the containment heat sink, assuming:

[0043] If the containment heat sink surface is covered by water, the containment node water temperature shall be used as the containment heat sink surface temperature;

[0044] If the containment heat sink surface is covered by gas, the containment heat sink surface temperature shall be the containment node gas temperature;

[0045] If the heat sink is horizontal and the water level is above the height of the heat sink surface, the heat sink surface is covered by water;

[0046] If the heat sink is vertical and the water coverage exceeds 50%, the heat sink is covered by water;

[0047] If the heat sink is made of steel, the temperature distribution through its thickness is assumed to be linear between its inner and outer surfaces;

[0048] If the heat sink is made of concrete, the temperature distribution from its inner or outer surface toward the center is assumed to follow a quadratic function within the thermal boundary layer adjacent to the inner or outer surface.

[0049] The analyzed and processed nuclear power plant severe accident simulation data is transmitted to the severe accident simulation system of the nuclear power plant technical support center, including:

[0050] After analysis and processing, the severe accident simulation data of nuclear power plants communicate with the nuclear power plant technical support center through MODBUS or OPC communication protocol;

[0051] Preset data collection frequency and data transmission path to ensure the real-time and stability of data;

[0052] The analyzed and processed nuclear power plant severe accident simulation data is transmitted to the severe accident simulator of the technical support center, thereby completing the data initialization of the severe accident simulator.

[0053] To achieve the above-mentioned purpose, the second embodiment of the present application proposes an external nuclear power plant severe accident simulation data driving device, comprising:

[0054] A data acquisition module is used to acquire the severe accident simulation data of the nuclear power plant in real time from the nuclear power plant database;

[0055] A data processing module is used to analyze and process the severe accident simulation data of the nuclear power plant, so that the severe accident simulation data of the nuclear power plant required to trigger the severe accident changes smoothly;

[0056] The data transmission module is used to transmit the analyzed and processed nuclear power plant severe accident simulation data to the severe accident simulation system of the nuclear power plant technical support center, providing a data source for subsequent severe accident simulator simulation calculations.

[0057] To achieve the above-mentioned purpose, the third aspect of the present application provides an electronic device, including: a processor, and a memory communicatively connected to the processor;

[0058] Memory stores computer-executable instructions;

[0059] The processor executes the computer-executable instructions stored in the memory to implement the method of the aforementioned technical solution.

[0060] To achieve the above-mentioned purpose, the fourth aspect embodiment of the present application proposes a computer-readable storage medium, in which computer execution instructions are stored. When the computer execution instructions are executed by a processor, they are used to implement the method as the aforementioned technical solution.

[0061] The present application provides an external nuclear power plant severe accident simulation data drive method, device, electronic device and storage medium, which calculates the thermal parameters, electrical performance parameters, core parameters and instrumentation parameters of the nuclear power plant system in real time, analyzes and processes the real-time parameter data calculated by the data acquisition module, including data compensation calculation, abnormal signal detection, and state pattern recognition, so that the thermal data required to trigger a severe accident changes smoothly without data step changes or oscillation changes; the processed data is transmitted to the severe accident simulation system of the technical support center to provide a data source for subsequent severe accident simulator simulation calculations. Through the present invention, it is possible to obtain the simulation data required to trigger a severe accident simulation without modifying the full-range simulator system, relying only on one host, that is, the severe accident simulator can complete the initialization startup according to the data provided by this driver.

[0062] Additional aspects and advantages of the present application will be given in part in the description below, and in part will become apparent from the description below, or will be learned through the practice of the present application. BRIEF DESCRIPTION OF THE DRAWINGS

[0063] The above and / or additional aspects and advantages of the present application will become apparent and easily understood from the following description of the embodiments in conjunction with the accompanying drawings, in which:

[0064] Figure 1 A flow chart of an external nuclear power plant severe accident simulation data-driven method provided in an embodiment of the present application;

[0065] Figure 2 A schematic structural diagram of an external nuclear power plant severe accident simulation data driving device provided in an embodiment of the present application. DETAILED DESCRIPTION

[0066] The embodiments of the present application are described in detail below, and examples of the embodiments are shown in the accompanying drawings, wherein the same or similar reference numerals throughout represent the same or similar elements or elements having the same or similar functions. The embodiments described below with reference to the accompanying drawings are exemplary and are intended to be used to explain the present application, and should not be construed as limiting the present application.

[0067] The following describes an external nuclear power plant severe accident simulation data driving method and device according to an embodiment of the present application with reference to the accompanying drawings.

[0068] Figure 1A flowchart of an external nuclear power plant severe accident simulation data-driven method provided in an embodiment of the present application. The method comprises the following steps:

[0069] Step 101, acquiring nuclear power plant severe accident simulation data from a nuclear power plant database in real time.

[0070] In the embodiment of the present invention, the nuclear power plant severe accident simulation data involved include thermal parameters, electrical performance parameters, core parameters and instrumentation parameters.

[0071] The thermal parameters are obtained by modeling the thermal parameters related systems of the primary and secondary loop systems of the nuclear power plant with high precision through thermal flow network modeling and then through model simulation; the thermal parameters at least include the reactor core temperature, the pressurizer pressure and the steam flow of the steam generator;

[0072] In the present invention, high-precision thermal flow network modeling is performed on the chemical and volume control system, passive containment cooling system, passive core cooling system, reactor coolant system, normal residual heat removal system, steam generator system and spent fuel pool cooling system in the primary loop system of a nuclear power plant, the main steam system and main feed water and startup feed water system of the secondary loop, and the containment system to simulate and calculate thermal parameters such as reactor core temperature, pressurizer pressure, and steam flow rate of the steam generator.

[0073] The electrical performance parameters are obtained by model simulation after high-precision electrical network modeling of the power supply system of the nuclear power plant; the electrical performance parameters include at least the current, voltage, active power and reactive power of the main generator and the standby generator, the current, voltage, active power and reactive power of the reactor coolant main pump, and the current, voltage, active power and reactive power of the main feed water system;

[0074] In the present invention, high-precision electrical network modeling is performed on the main AC power supply system, non-1E-level DC and UPS system and 1E-level DC and UPS system to simulate and calculate the electrical performance parameters such as current, voltage, active power and reactive power of major equipment such as main generators and backup generators, reactor coolant main pumps, and main feed water pumps.

[0075] The core parameters are obtained by model simulation after high-precision reactor core dynamics modeling of the nuclear power plant reactor main system; the core parameters at least include reactor neutron flux, decay heat and radioactive source terms;

[0076] The instrumentation and control parameters are obtained through model simulation after high-precision control logic modeling and human-machine operation screen modeling of the systems involved in the thermal, electrical and core models of the nuclear power plant; the control parameters at least include the logical operation parameters of the DCS control system.

[0077] Step S102: Analyze and process the nuclear power plant severe accident simulation data to make the nuclear power plant severe accident simulation data required to trigger a severe accident change smoothly.

[0078] Specifically, data recognition is performed on the severe accident simulation data of nuclear power plants, and the severe accident simulation data of nuclear power plants are divided into calculation processing parameters and specific processing parameters according to whether the change of the calculation results of the parameters in the process of triggering severe accidents is stable without step oscillation;

[0079] For the calculation and processing parameters, a smooth transition algorithm is used for processing;

[0080] High-performance computing chips and optimization algorithms are used to quickly process the collected data. The mass, energy, temperature, pressure, cavitation fraction and water level of each control body node or equipment; the fluid flow rate of each connection node, including liquid, steam and non-condensable gas; the temperature of each thermal component node, including the fuel element node temperature, cladding temperature, control rod node temperature, as well as the wall temperature of the pressure vessel, pressurizer, main pipeline, etc. and the temperature of the thermal component and shell wall of the containment are processed using a smooth transition algorithm to ensure that the calculation results of these parameters change smoothly without step oscillations during the process of triggering a severe accident.

[0081] The smooth transition algorithm formula used for calculating processing parameters is expressed as:

[0082]

[0083] Among them, X d is the calculation processing parameter, X dis Smooth transition algorithm calculation, X m is the value calculated by the severe accident program, t s is the time to trigger a severe accident, Δt r is the transition period, and t is the current operation time.

[0084] For specific processing parameters, specific processing is performed according to the data type.

[0085] Specifically, the specific processing parameter is the severe accident simulation calculation time. When a severe accident is triggered, the current time is transmitted to the start-up time of the severe accident simulator; if the reactor is shut down, or the reactor coolant main pump trips before the severe accident is triggered, the corresponding severe accident event mark is set according to the data calculated and transmitted from the smooth transition algorithm and the time of the reactor shutdown or the reactor coolant main pump trip is recorded, and the attenuation power is calculated according to the difference between the time of triggering the severe accident and the time of the reactor shutdown or the pump trip;

[0086] The specific processing parameters are the physical properties of the system nodes. The mass and energy of the node are calculated based on the water and gas temperature, pressure and average cavitation fraction data in each system node. If the cavitation fraction is less than 1.0*e -6 , the node is assumed to be a water entity; if the cavitation fraction is greater than 0.999999, the node is assumed to be filled with superheated steam; if the void fraction is 1.0*e -6 and 0.999999, the node is assumed to be filled with a two-phase mixture of steam and water; if the temperature difference between water and steam is less than 1.0K, and the void fraction is less than 0.6, the water and steam phases are assumed to be in thermal equilibrium;

[0087] The specific processing parameters are the pressurizer gas-liquid state, the water level in the pressurizer is used as input, and the conditions of "water entity" condition or "steam fill" condition are determined based on the collapsed water level;

[0088] The specific processing parameter is the water level on the secondary side of the steam generator. The input of the secondary side conditions of the steam generator includes pressure, collapse water level in the downcomer, and water and gas temperature. The thermal hydraulic model of the steam generator is a dual-zone model, in which the area in contact with the tube bundle and the steam-water separator is set as zone 1, and the downcomer and the dome are set as zone 2. Based on the collapse water level in the downcomer, the water and gas space properties in zone 2 are calculated, and the collapse water level in zone 1 is set to be the same as the collapse water level in zone 2. This assumption of the same water level is applicable to the case where there is no obvious heat transfer from the primary side to the secondary side, and there is no obvious discharge from the steam generator.

[0089] The specific processing parameters are the water-gas properties in the pressure relief tank, which are calculated based on the water and gas temperature, pressure and cavitation fraction in the pressure relief tank; if the bursting disk is intact, the pressure relief tank is assumed to be filled with uniformly mixed water and steam; if the bursting disk is ruptured, it is assumed that the liquid phase and the gas phase are separated, and the hypothetical pressure relief tank is filled with water, steam and air;

[0090] The specific treatment parameters are the reactor coolant system heat sink temperature. The reactor coolant system heat sink includes the reactor vessel wall, cold leg and hot leg walls, and steam generator heat transfer tubes. Except for the steam generator heat transfer tubes, the temperature of the heat sink does not need to be provided. Instead, it is assumed that:

[0091] If the inner and / or outer surfaces of the heat sink are in contact with a reactor coolant system node, the surface temperature is very close to the reactor coolant system water or gas temperature, depending on whether the heat sink surface is covered by water or gas;

[0092] If the inner or outer surface of the heat sink is in contact with the containment node, the heat transfer coefficient h between the heat sink and the containment node is cThe heat sink temperature T is calculated from the heat loss from the reactor coolant system to the containment under steady-state conditions. o The energy balance based on the surface is given by:

[0093]

[0094] Among them, k s is the thermal conductivity of the heat sink, Δx s is the thickness of the heat sink, T i is the temperature on the other side of the heat sink in contact with the reactor coolant system node, T o is the water or gas temperature in the containment node;

[0095] For the steam generator heat transfer tube, the temperature distribution on the heat sink thickness is assumed to be a linear function, and the inner and outer surface temperatures calculated by the smooth transition algorithm are used as input;

[0096] The specific processing parameters are the fuel and cladding temperatures, and the calculation of the heat transfer coefficient from the cladding to the water before calculating the fuel and cladding temperatures and energies at the time of triggering a severe accident;

[0097] If the reactor coolant main pump is in operation or has tripped before a severe accident is triggered, the flow rate through the core is calculated from the reactor coolant main pump curve or the fallback curve;

[0098] The heat transfer coefficient is calculated based on the forced circulation relationship. If the trip time of the reactor coolant main pump exceeds the preset time, the heat transfer coefficient is 100W / ㎡·℃, and the decay power at the time of switching is used to calculate the heat flux density from the cladding to the water. The temperature of the cladding and fuel is determined by the energy balance relationship from the fuel center to the water.

[0099] The specific processing parameters are the mass and energy of water and gas in the containment node, using the total pressure, partial pressures of steam, water and gas temperature, and the collapsed water level in the containment node as input; the water and gas in the containment are assumed to be separate and have their own specific temperatures, and the volume occupied by water and gas is calculated based on the water level in the containment node; the mass and energy of water are calculated based on the water temperature and the total pressure; the gas in the containment node is assumed to be a mixture of steam and air, the steam partial pressure is provided by the smoothing algorithm, and the air partial pressure is calculated from the difference between the total pressure and the steam partial pressure, and the gas mass and energy are calculated based on the partial pressure and the gas temperature;

[0100] The specific treatment parameter is the temperature of the containment heat sink, assuming:

[0101] If the containment heat sink surface is covered by water, the containment node water temperature shall be used as the containment heat sink surface temperature;

[0102] If the containment heat sink surface is covered by gas, the containment heat sink surface temperature shall be the containment node gas temperature;

[0103] If the heat sink is horizontal and the water level is above the height of the heat sink surface, the heat sink surface is covered by water;

[0104] If the heat sink is vertical and the water coverage exceeds 50%, the heat sink is covered by water;

[0105] If the heat sink is made of steel, the temperature distribution through its thickness is assumed to be linear between its inner and outer surfaces;

[0106] If the heat sink is made of concrete, the temperature distribution from its inner or outer surface toward the center is assumed to follow a quadratic function within the thermal boundary layer adjacent to the inner or outer surface.

[0107] Step S103: Transmitting the analyzed and processed nuclear power plant severe accident simulation data to the severe accident simulation system of the nuclear power plant technical support center to provide a data source for subsequent severe accident simulator simulation calculations.

[0108] Data communication is carried out with the technical support center through communication protocols such as MODBUS and OPC. At the same time, the data transmission module can preset the data collection frequency and data transmission path to ensure the real-time and stability of the data, and transmit the processed data to the severe accident simulator of the technical support center, thereby completing the data initialization of the severe accident simulator.

[0109] Figure 2 A schematic structural diagram of an external nuclear power plant severe accident simulation data driving device provided in an embodiment of the present application.

[0110] like Figure 2 As shown, the device 300 includes:

[0111] The data acquisition module 310 is used to acquire the severe accident simulation data of the nuclear power plant in real time from the nuclear power plant database;

[0112] The data processing module 320 is used to analyze and process the nuclear power plant severe accident simulation data, so that the nuclear power plant severe accident simulation data required to trigger a severe accident changes smoothly;

[0113] The data transmission module 330 is used to transmit the analyzed and processed nuclear power plant severe accident simulation data to the severe accident simulation system of the nuclear power plant technical support center, providing a data source for subsequent severe accident simulator simulation calculations.

[0114] It should be noted that the above explanation of the embodiment of the external nuclear power plant severe accident simulation data driving method is also applicable to the external nuclear power plant severe accident simulation data driving device of this embodiment, and will not be repeated here.

[0115] In order to implement the above embodiments, the present application also proposes an electronic device, comprising: a processor, and a memory communicatively connected to the processor; the memory stores computer-executable instructions; the processor executes the computer-executable instructions stored in the memory to implement the method provided by the above embodiments.

[0116] In order to implement the above embodiments, the present application also proposes a computer-readable storage medium, in which computer-executable instructions are stored. When the computer-executable instructions are executed by a processor, they are used to implement the methods provided by the above embodiments.

[0117] In order to implement the above embodiments, the present application also proposes a computer program product, including a computer program, which implements the methods provided by the above embodiments when executed by a processor.

[0118] The collection, storage, use, processing, transmission, provision and disclosure of user personal information involved in this application are in compliance with relevant laws and regulations and do not violate public order and good morals.

[0119] It should be noted that personal information from users should be collected for legitimate and reasonable purposes and should not be shared or sold outside of these legitimate uses. In addition, such collection / sharing should be carried out after receiving the user's informed consent, including but not limited to notifying the user to read the user agreement / user notice and sign the agreement / authorization including authorization of relevant user information before the user uses the function. In addition, any necessary steps should be taken to protect and safeguard access to such personal information data and ensure that others who have access to personal information data comply with its privacy policy and procedures.

[0120] The present application is expected to provide an implementation scheme for users to selectively block the use or access of personal information data. That is, the present disclosure is expected to provide hardware and / or software to prevent or block access to such personal information data. Once the personal information data is no longer needed, the risk can be minimized by limiting data collection and deleting the data. In addition, when applicable, such personal information is de-identified to protect the privacy of the user.

[0121] In the description of the aforementioned embodiments, the description with reference to the terms "one embodiment", "some embodiments", "example", "specific example", or "some examples" etc. means that the specific features, structures, materials or characteristics described in conjunction with the embodiment or example are included in at least one embodiment or example of the present application. In this specification, the schematic representations of the above terms do not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials or characteristics described may be combined in any one or more embodiments or examples in a suitable manner. In addition, those skilled in the art may combine and combine the different embodiments or examples described in this specification and the features of the different embodiments or examples, without contradiction.

[0122] In addition, the terms "first" and "second" are used for descriptive purposes only and should not be understood as indicating or implying relative importance or implicitly indicating the number of the indicated technical features. Therefore, the features defined as "first" and "second" may explicitly or implicitly include at least one of the features. In the description of this application, the meaning of "plurality" is at least two, such as two, three, etc., unless otherwise clearly and specifically defined.

[0123] Any process or method description in a flowchart or otherwise described herein may be understood to represent a module, fragment or portion of code comprising one or more executable instructions for implementing the steps of a custom logical function or process, and the scope of the preferred embodiments of the present application includes alternative implementations in which functions may not be performed in the order shown or discussed, including performing functions in a substantially simultaneous manner or in the reverse order depending on the functions involved, which should be understood by technicians in the technical field to which the embodiments of the present application belong.

[0124] The logic and / or steps represented in the flowchart or otherwise described herein, for example, can be considered as an ordered list of executable instructions for implementing logical functions, and can be embodied in any computer-readable medium for use by an instruction execution system, device or apparatus (such as a computer-based system, a system including a processor, or other system that can fetch instructions from an instruction execution system, device or apparatus and execute the instructions), or in combination with these instruction execution systems, devices or apparatuses. For the purpose of this specification, "computer-readable medium" can be any device that can contain, store, communicate, propagate or transmit a program for use by an instruction execution system, device or apparatus, or in combination with these instruction execution systems, devices or apparatuses. More specific examples of computer-readable media (a non-exhaustive list) include the following: an electrical connection with one or more wires (electronic device), a portable computer disk box (magnetic device), a random access memory (RAM), a read-only memory (ROM), an erasable and programmable read-only memory (EPROM or flash memory), a fiber optic device, and a portable compact disk read-only memory (CDROM). In addition, the computer-readable medium may even be paper or other suitable medium on which the program is printed, since the program may be obtained electronically, for example, by optically scanning the paper or other medium and then editing, interpreting or processing in other suitable ways if necessary, and then stored in a computer memory.

[0125] It should be understood that the various parts of the present application can be implemented by hardware, software, firmware or a combination thereof. In the above-mentioned embodiments, multiple steps or methods can be implemented by software or firmware stored in a memory and executed by a suitable instruction execution system. For example, if implemented by hardware, as in another embodiment, it can be implemented by any one of the following technologies known in the art or their combination: a discrete logic circuit having a logic gate circuit for implementing a logic function for a data signal, a dedicated integrated circuit having a suitable combination of logic gate circuits, a programmable gate array (PGA), a field programmable gate array (FPGA), etc.

[0126] A person skilled in the art may understand that all or part of the steps in the method for implementing the above-mentioned embodiment may be completed by instructing related hardware through a program, and the program may be stored in a computer-readable storage medium, which, when executed, includes one or a combination of the steps of the method embodiment.

[0127] In addition, each functional unit in each embodiment of the present application may be integrated into a processing module, or each unit may exist physically separately, or two or more units may be integrated into one module. The above-mentioned integrated module may be implemented in the form of hardware or in the form of a software functional module. If the integrated module is implemented in the form of a software functional module and sold or used as an independent product, it may also be stored in a computer-readable storage medium.

[0128] The storage medium mentioned above may be a read-only memory, a magnetic disk or an optical disk, etc. Although the embodiments of the present application have been shown and described above, it can be understood that the above embodiments are exemplary and cannot be understood as limiting the present application. A person of ordinary skill in the art may change, modify, replace and modify the above embodiments within the scope of the present application.

Claims

1. A data-driven method for simulating severe accidents in an external nuclear power plant, characterized in that: include: Acquire nuclear power plant severe accident simulation data in real time from the nuclear power plant database; Analyzing and processing the nuclear power plant severe accident simulation data so that the nuclear power plant severe accident simulation data required to trigger a severe accident changes smoothly; The analyzed and processed nuclear power plant severe accident simulation data is transmitted to the severe accident simulation system of the nuclear power plant technical support center to provide a data source for subsequent severe accident simulator simulation calculations.

2. The external nuclear power plant severe accident simulation data driving method according to claim 1 is characterized in that: The nuclear power plant severe accident simulation data includes thermal parameters, electrical performance parameters, core parameters and instrumentation parameters; wherein, The thermal parameters are obtained by model simulation after high-precision thermal flow network modeling of thermal parameter related systems in the primary and secondary loop systems of the nuclear power plant; the thermal parameters at least include reactor core temperature, pressurizer pressure and steam generator steam flow; The electrical performance parameters are obtained by model simulation after high-precision electrical network modeling of the power supply system of the nuclear power plant; the electrical performance parameters at least include the current, voltage, active power and reactive power of the main generator and the standby generator, the current, voltage, active power and reactive power of the reactor coolant main pump, and the current, voltage, active power and reactive power of the main feed water system; The core parameters are obtained by model simulation after high-precision reactor core dynamics modeling is performed on the nuclear power plant reactor main system; the core parameters at least include reactor neutron flux, decay heat and radioactive source terms; The instrumentation and control parameters are obtained through model simulation after high-precision control logic modeling and human-machine operation screen modeling of the systems involved in the thermal, electrical and core models of the nuclear power plant; the control parameters at least include the logical operation parameters of the DCS control system.

3. The external nuclear power plant severe accident simulation data driving method according to claim 1 is characterized in that: The analyzing and processing of the nuclear power plant severe accident simulation data includes: Performing data identification on the nuclear power plant severe accident simulation data, and dividing the nuclear power plant severe accident simulation data into calculation processing parameters and specific processing parameters according to whether the change of the calculation result of the parameter in the process of triggering the severe accident is stable without step oscillation; For the calculation processing parameters, a smooth transition algorithm is used for processing; For the specific processing parameters, specific processing is performed according to the data type.

4. The external nuclear power plant severe accident simulation data driving method according to claim 3 is characterized in that: The types of calculation and processing parameters include: the mass, energy, temperature, pressure, cavitation fraction and water level of each control body node or equipment in the nuclear power plant; the fluid flow rate of each connection node, including liquid, steam and non-condensable gas; the temperature of each thermal component node, including the fuel element node temperature, cladding temperature, control rod node temperature, as well as the wall temperature of the pressure vessel, stabilizer, main pipeline, and the containment thermal component and shell wall temperature.

5. The external nuclear power plant severe accident simulation data driving method according to claim 3 is characterized in that: The smooth transition algorithm formula used for the calculation processing parameters is expressed as: Among them, X d is the calculation processing parameter, X dis Smooth transition algorithm calculation, X m is the value calculated by the severe accident program, t s is the time to trigger a severe accident, Δt r is the transition period, and t is the current operation time.

6. The external nuclear power plant severe accident simulation data driving method according to claim 3 is characterized in that: The specific processing parameters are processed specifically according to the data type, including: The specific processing parameter is the severe accident simulation calculation time. When a severe accident is triggered, the current time is transmitted to the start-up time of the severe accident simulator. If the reactor is shut down or the reactor coolant main pump trips before the severe accident is triggered, the corresponding severe accident event mark is set according to the data calculated and transmitted from the smooth transition algorithm and the time of the reactor shutdown or the reactor coolant main pump trip is recorded. The attenuation power is calculated according to the difference between the time of triggering the severe accident and the time of the reactor shutdown or the pump trip. The specific processing parameters are the physical properties of the system nodes. The mass and energy of the node are calculated based on the water and gas temperature, pressure and average cavitation fraction data in each system node. If the cavitation fraction is less than 1.0*e -6 , the node is assumed to be a water entity; if the cavitation fraction is greater than 0.999999, the node is assumed to be filled with superheated steam; if the void fraction is 1.0*e -6 and 0.999999, the node is assumed to be filled with a two-phase mixture of steam and water; if the temperature difference between water and steam is less than 1.0K, and the void fraction is less than 0.6, the water and steam phases are assumed to be in thermal equilibrium; The specific processing parameter is the gas-liquid state of the pressurizer, the water level in the pressurizer is used as input, and the conditions of the "water entity" condition or the "steam fill" condition are determined based on the collapsed water level; The specific processing parameter is the water level on the secondary side of the steam generator, and the input of the secondary side conditions of the steam generator includes pressure, the collapsed water level in the descending section, and the water and gas temperatures; the thermal hydraulic model of the steam generator is a dual-region model, in which the area in contact with the tube bundle and the steam-water separator is set as region 1, and the descending section and the dome are set as region 2, based on the collapsed water level in the descending section, the water and gas space properties in region 2 are calculated, and the collapsed water level in region 1 is set to be the same as the collapsed water level in region 2, and this assumption of the same water level is applicable to the case where there is no obvious heat transfer from the primary side to the secondary side, and there is no obvious discharge from the steam generator; The specific processing parameters are the water-gas properties in the pressure relief box, which are calculated based on the water and gas temperature, pressure and cavitation fraction in the pressure relief box; if the bursting disc is intact, it is assumed that the pressure relief box is filled with uniformly mixed water and steam; if the bursting disc is ruptured, it is assumed that the liquid phase and the gas phase are separated, and the false pressure relief box is filled with water, steam and air; The specific processing parameters are the reactor coolant system heat sink temperature, the reactor coolant system heat sink includes the reactor vessel wall, cold leg and hot leg walls, steam generator heat transfer tubes, except for the steam generator heat transfer tubes, the temperature of the heat sink does not need to be provided, instead, it is assumed that: If the inner and / or outer surfaces of the heat sink are in contact with a reactor coolant system node, the surface temperature is very close to the reactor coolant system water or gas temperature, depending on whether the heat sink surface is covered by water or gas; If the inner or outer surface of the heat sink is in contact with the containment node, the heat transfer coefficient h between the heat sink and the containment node is c The heat sink temperature T is calculated from the heat loss from the reactor coolant system to the containment under steady-state conditions. o The energy balance based on the surface is given by: Among them, k s is the thermal conductivity of the heat sink, Δx S is the thickness of the heat sink, T i is the temperature on the other side of the heat sink in contact with the reactor coolant system node, T c is the water or gas temperature in the containment node; For the steam generator heat transfer tube, the temperature distribution on the heat sink thickness is assumed to be a linear function, and the inner and outer surface temperatures calculated by the smooth transition algorithm are used as input; The specific processing parameters are the fuel and cladding temperatures, and the calculation of the heat transfer coefficient from the cladding to the water before calculating the fuel and cladding temperatures and energies when a severe accident is triggered; If the reactor coolant main pump is in operation or has tripped before a severe accident is triggered, the flow rate through the core is calculated from the reactor coolant main pump curve or the fallback curve; The heat transfer coefficient is calculated based on the forced circulation relationship. If the trip time of the reactor coolant main pump exceeds the preset time, the decay power at the time of switching with a heat transfer coefficient of 100W / ㎡·℃ is used to calculate the heat flux density from the cladding to the water. The temperature of the cladding and fuel is determined by the energy balance relationship from the fuel center to the water. The specific processing parameters are the mass and energy of water and gas in the closed node, using the total pressure, partial pressures of steam, water and gas temperature and the collapsed water level in the containment node as input; assuming that the water and gas in the containment are separate and have their own specific temperatures, the volume occupied by water and gas is calculated based on the water level in the containment node; the mass and energy of water are calculated based on the water temperature and the total pressure; the gas in the containment node is assumed to be a mixture of steam and air, the steam partial pressure is provided by a smooth transition algorithm, and the air partial pressure is calculated by the difference between the total pressure and the steam partial pressure, and the gas mass and energy are calculated based on the partial pressure and the gas temperature; The specific processing parameter is the temperature of the containment heat sink, assuming: If the containment heat sink surface is covered by water, the containment node water temperature shall be used as the containment heat sink surface temperature; If the containment heat sink surface is covered by gas, the containment heat sink surface temperature shall be the containment node gas temperature; If the heat sink is horizontal and the water level is above the height of the heat sink surface, the heat sink surface is covered by water; If the heat sink is vertical and the water coverage exceeds 50%, the heat sink is covered by water; If the heat sink is made of steel, the temperature distribution through its thickness is assumed to be linear between its inner and outer surfaces; If the heat sink is made of concrete, the temperature distribution from its inner or outer surface toward the center is assumed to follow a quadratic function within the thermal boundary layer adjacent to the inner or outer surface.

7. The external nuclear power plant severe accident simulation data driving method according to claim 1, characterized in that: The method of transmitting the analyzed and processed nuclear power plant severe accident simulation data to the severe accident simulation system of the nuclear power plant technical support center includes: After analysis and processing, the severe accident simulation data of nuclear power plants communicate with the nuclear power plant technical support center through MODBUS or OPC communication protocol; Preset data collection frequency and data transmission path to ensure the real-time and stability of data; The analyzed and processed nuclear power plant severe accident simulation data is transmitted to the severe accident simulator of the technical support center, thereby completing the data initialization of the severe accident simulator.

8. An external nuclear power plant severe accident simulation data driving device, characterized in that: include: A data acquisition module is used to acquire the severe accident simulation data of the nuclear power plant in real time from the nuclear power plant database; A data processing module, used for analyzing and processing the nuclear power plant severe accident simulation data, so that the nuclear power plant severe accident simulation data required to trigger a severe accident changes smoothly; The data transmission module is used to transmit the analyzed and processed nuclear power plant severe accident simulation data to the severe accident simulation system of the nuclear power plant technical support center, providing a data source for subsequent severe accident simulator simulation calculations.

9. An electronic device, characterized in that: include: A processor, and a memory communicatively connected to the processor; The memory stores computer-executable instructions; The processor executes the computer-executable instructions stored in the memory to implement the method according to any one of claims 1 to 7.

10. A computer-readable storage medium, characterized in that: The computer-readable storage medium stores computer-executable instructions, which are used to implement the method according to any one of claims 1 to 7 when executed by a processor.

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