VVER type three-dimensional accident scene data coupling analysis method

Abstract

The invention belongs to the technical field of VVER type nuclear power units. The method aims to solve the problems of VVER reactor type nuclear power plant model building, VVER reactor type three-dimensional dynamic effect manufacturing, VVER reactor type important parameter monitoring interface manufacturing, VVER reactor type nuclear power plant accident and online scene database construction, VVER reactor type nuclear power plant accident / online scene data and model point table mapping and coupling linkage, VVER reactor type nuclear power plant accident / online scene data and model point table modeling and VVER reactor type nuclear power plant accident / online scene data and model point table modeling. The invention relates to a VVER reactor type nuclear power plant three-dimensional accident and real-time online scene dynamic process display problem. The invention discloses a VVER pile type three-dimensional accident scene data coupling analysis method, serious accident bottom layer data and online real-time data stored in a Redis database are taken as driving data, data acquisition and mapping of a point file corresponding relation on Redis are realized in combination with a data communication interface, and real-time real scene data of a power plant side are accessed, so that the real-time scene data of the power plant side can be acquired, and the real-time scene data of the power plant side can be acquired. And dynamically displaying the development process on line.

Description

Technical Field

[0001] The present application belongs to the technical field of VVER nuclear power units, and in particular to a method for coupling analysis of VVER reactor three-dimensional accident scenario data. Background Art

[0002] VVER nuclear power units are pressurized water reactor nuclear power units developed and designed by Russia, mainly including VVER-1000 and VVER-1200. At present, many domestic nuclear power plants use or build VVER nuclear power units, and the total installed capacity of VVER reactors will reach 8,600MW. VVER reactors account for a relatively high proportion of reactors besides M310, Hualong One, and AP1000.

[0003] A severe accident is a series of processes that lead to the leakage of radioactive materials when there is a threat of large-scale fuel cladding failure in the core of a nuclear reactor, or the integrity of the pressure vessel or containment of a nuclear power plant is damaged. Such accidents may be triggered by a variety of factors, such as specific accidents or transients during the operation of the reactor, multiple failures of dedicated safety facilities, or misjudgments by operators during operation. As the amount of water in the primary circuit decreases, core cooling cannot be guaranteed, which may cause the core to overheat and melt, and eventually develop into a severe accident. Summary of the invention

[0004] The purpose of this application is to provide a VVER reactor type three-dimensional accident scenario data coupling analysis method to solve the problems of VVER reactor type nuclear power plant model construction, VVER reactor type three-dimensional dynamic effect production, VVER reactor type important parameter monitoring interface production, VVER reactor type nuclear power plant accident and online scenario database construction, VVER reactor type nuclear power plant accident / online scenario data and model point table mapping and coupling linkage, VVER reactor type nuclear power plant three-dimensional accident and real-time online scenario dynamic process display.

[0005] In order to achieve the above objectives, this application provides the following technical solutions:

[0006] The present application provides a VVER reactor type three-dimensional accident scenario data coupling analysis method, comprising:

[0007] Step 1: Based on the structural characteristics of the VVER reactor, a three-dimensional visualization model of the VVER reactor primary loop, pressure vessel, pressurizer, steam generator, containment, and spent fuel pool is constructed;

[0008] Step 2: Create three-dimensional dynamic effects of the VVER reactor primary loop, pressure vessel, pressurizer, steam generator, containment, and spent fuel pool in normal and accident conditions;

[0009] Step 3: Create an important parameter monitoring interface for monitoring VVER reactor type severe accidents and online scenarios;

[0010] Step 4: Build the underlying database, including internal and external data;

[0011] Step 5: Construct a mapping point table between the underlying data and the VVER type three-dimensional accident and the online scene front-end display interface. Use the underlying data of severe accidents stored in the Redis database and the online real-time data as driving data, and combine the data communication interface to realize the mapping of data collection and point file correspondence on Redis.

[0012] Step 6: Dynamically display the three-dimensional accident process and real-time online process.

[0013] In some embodiments, step 1 specifically includes:

[0014] Step 1.1: Make a three-dimensional visualization model of the primary circuit, including the primary circuit pipeline, 1# steam generator SG1, 2# steam generator SG2, 3# steam generator SG3, 4# steam generator SG4, stabilizer, pressure vessel, and main pump;

[0015] Step 1.2: Make a three-dimensional visualization model of the pressure vessel, including the pressure vessel body, the reactor cavity, and the connected pipes;

[0016] Step 1.3: Make a three-dimensional visualization model of the pressure stabilizer, including the pressure stabilizer body, pressure relief pipeline and valve, and pressure relief box;

[0017] Step 1.4: Make a 3D visualization model of the steam generator, including the steam generator body, feedwater pipeline and valve, steam pipeline and valve;

[0018] Step 1.5: Make a three-dimensional visualization model of the containment, including the containment section, nuclear island auxiliary plant, refueling pool, spent fuel pool, spray system, primary circuit main equipment and pipelines, ring hanger, lighting, core melt catcher and its cooling facilities;

[0019] Step 1.6: Create a 3D visualization model of the spent fuel pool, including the spent fuel pool, wall, fuel assembly, ring hanger, and lighting.

[0020] In some embodiments, step 2 specifically includes:

[0021] Step 2.1: Create dynamic effects of pressure and temperature changes in the primary circuit system;

[0022] Step 2.2: Create dynamic effects of the working fluid loading in the volume equipment and spent fuel pool;

[0023] Step 2.3: Create dynamic flow effects of water and air inside the pipe;

[0024] Step 2.4: Create dynamic effects of bubbles inside the pipe;

[0025] Step 2.5: Create dynamic effects of heat exchange equipment and internal steam flow;

[0026] Step 2.6: Create dynamic effects of pipeline rupture and fluid spraying;

[0027] Step 2.7: Create dynamic effects of the rupture of the steam generator heat transfer tube and the spraying of working fluid;

[0028] Step 2.8: Create dynamic effects of main steam pipe rupture and working fluid spraying;

[0029] Step 2.9: Create the dynamic effect of the pressure relief valve of the pressure regulator to release the working fluid;

[0030] Step 2.10: Create the dynamic effect of the spent fuel pool breach and fluid spraying;

[0031] Step 2.11: Create dynamic effects of core changes;

[0032] Step 2.12: Create dynamic effects of core heating, melting, melt flow, core collapse, melt entering the lower head, melt accumulation in the lower head, lower head heating, failure, melt entering the core catcher and reacting with the fillings therein;

[0033] Step 2.13: Make a dynamic effect of the core catcher to collect the core melt;

[0034] Step 2.14: Create dynamic effects of spent fuel heating, melting, melt flow, collapse, melt falling to the bottom of the spent fuel pool, melt accumulation at the bottom of the spent fuel pool, and heating of the bottom of the spent fuel pool;

[0035] Step 2.15: Create dynamic effects of changes in pressure, temperature, radioactivity, and hydrogen concentration in the containment under accident conditions;

[0036] Step 2.16: Create dynamic effects of steam in the containment;

[0037] Step 2.17: Create a dynamic effect of containment spraying on the containment;

[0038] Step 2.18: Create a dynamic effect of the pit water level change.

[0039] In some embodiments, step 3 specifically includes:

[0040] Step 3.1: Create a Shapiro diagram interface to display the changes in the content of air, combustible gas, and inert gas in the containment;

[0041] Step 3.2: Create a parameter curve interface to display the curve graph of key parameters changing over time;

[0042] Step 3.3: Create a main parameter interface to display the changes of main parameter values ​​over time;

[0043] Step 3.4: Create a core parameter interface, including a core parameter 2D interface and a core temperature parameter 3D interface;

[0044] Step 3.5: Create an off-site dose distribution interface to display the off-site depth dose rate, internal effective dose rate, and total effective dose rate values ​​changing over time;

[0045] Step 3.6: Create a message output interface to display the key events and corresponding times that occurred during the accident process;

[0046] Step 3.7: Create the containment parameter interface, including the reactor pit, lower compartment, upper large space, annular space, refueling pool, upper auxiliary building, lower auxiliary building, control room, fuel loading and unloading area, and spent fuel pool;

[0047] Step 3.8: Create the spent pool parameter interface, including spent pool parameters Figure 2 D interface and depletion pool parameters Figure 3 D interface;

[0048] Step 3.9: Create an online scene monitoring interface to display the numerical changes of important parameters of equipment structures such as the primary loop, pressure vessel, pressurizer, steam generator, containment, spent fuel pool, etc. in the online scene, such as spent fuel pool temperature, steam generator liquid level, pressure, feed water flow, pressurizer water level, temperature, core outlet temperature, containment temperature, hydrogen concentration, pump feed water flow, and dynamic numerical changes of parameters such as water temperature and flow of each loop. In some embodiments, the key parameters include key parameters of equipment structures such as the primary loop, pressure vessel, pressurizer, steam generator, containment, spent fuel pool, etc., such as containment temperature, pressure vessel water level, loop1 cold section water temperature, loop1 hot section water temperature, steam generator liquid level, etc.

[0049] In some embodiments, the main parameters include the main parameters of the primary circuit, pressure vessel, pressurizer, steam generator, containment, spent fuel pool and other equipment structures, such as the maximum core temperature, power, pressure vessel top pressure, containment gas concentration, primary circuit water temperature, steam generator secondary side pressure, pressurizer spray flow, etc. In some embodiments, the core parameter 2D interface is used to display the core fuel temperature and fuel mass values ​​changing with time, and the core temperature parameter 3D interface is used to display the three-dimensional interface of the core node.

[0050] In some embodiments, step 4 specifically includes:

[0051] Step 4.1: Store the static accident scenario data calculated by the integrated severe accident analysis program in the Redis database;

[0052] Step 4.2: Store external data in the Redis database, and the external data communication interface communicates through the network;

[0053] Step 4.3: When sending data, the conversion relationship in the configuration file will be used to convert the Chinese name of the variable into the variable name, and the data will be converted into structured data and sent to the external database; when receiving data, the received structured data will be converted into the corresponding variable value and stored in the Redis database.

[0054] In some embodiments, step 5 specifically includes:

[0055] Step 5.1: Configure the data type, data file location, database IP, port, scene and effect, and data name, point name, and unit of all pages;

[0056] Step 5.2: Configure the point table. The data communication interface provides the correspondence between the front-end three-dimensional dynamic effects, Shapiro diagram interface, parameter curve interface, main parameter interface, core parameter interface, off-site dose distribution interface, message output interface, containment parameter interface, spent pool parameter interface, and online scene monitoring interface and the underlying database point names; use the conversion relationship in the configuration file to convert the Chinese name of the variable into the variable name, and then find the corresponding key-value pair in the underlying static data to realize fast reading of data.

[0057] In some embodiments, step 6 specifically includes:

[0058] Step 6.1: Sort out the simulation calculation parameters, extract the parameters required for the 3D model, and pre-process according to the display requirements;

[0059] Step 6.2: Link the internal accident sequence scene data, the 3D display model of the 3D scene, the Shapiro diagram interface, the parameter curve interface, the main parameter interface, the core parameter interface, the off-site dose distribution interface, the message output interface, the containment parameter interface, and the spent pool parameter interface;

[0060] Step 6.3: Link the external real-time online data, the three-dimensional display model of the screen in the three-dimensional scene, and the online scene monitoring interface; Step 6.4: Drive the screen to display the severe accident scene of the VVER reactor type, and display the status and phenomena in the key equipment or system of the nuclear power plant in real time during the severe accident.

[0061] Compared with the prior art, the VVER reactor type three-dimensional accident scenario data coupling analysis method provided in this application has the following beneficial effects:

[0062] This application realizes the coupling and linkage of typical accident sequence scenario data and three-dimensional simulation models, driving typical nuclear accident scenarios in 3D display screens. At the same time, the three-dimensional accident scene display can support covering various typical serious accident scenarios, and has the ability to access real-time real scene data on the power plant side and dynamically display the development process online.

[0063] Furthermore, this application uses an integrated severe accident analysis program to simulate and calculate 12 typical accident scenarios, including large / medium / small ruptures in cold pipe sections, large / medium / small ruptures in hot pipe sections, power outages in the entire plant, ruptures in single / multiple heat transfer pipes in steam generators, ruptures in main steam pipes, loss of main feed water, and water loss in spent fuel pools. Based on the Redis database, an external general data coupling interface is developed to access real-time data from the power plant side.

[0064] Furthermore, the present application studies the coupling analysis method of accident scenario data and models, couples typical accident scenario data, real-time online data and scenario special effects, drives the screen to display typical nuclear accident scenarios and real-time online scenarios of VVER reactors, and displays the status and phenomena of key equipment or systems of nuclear power plants during severe accidents and real-time online. Severe accident scenarios include water vapor, water flow, bubbles, equipment level changes, core meltdown, core catcher collecting molten material, breach spraying, containment spraying, pit level, spent fuel meltdown and other effects. At the same time, you can choose to enter the Shapiro diagram, parameter curve, main parameters, core parameters, off-site dose distribution, message output, containment parameters, spent pool parameter diagram and other interfaces to query related parameters. In the real-time online scenario, the status and phenomena of key equipment or systems of online nuclear power plants on the power plant side are displayed, including effects such as water vapor, water flow, bubbles, equipment level changes, etc. At the same time, you can enter the online scene monitoring interface to query related parameters, and realize online dynamic display of the accident development process, providing support for accident analysis and emergency decision-making. BRIEF DESCRIPTION OF THE DRAWINGS

[0065] In order to more clearly illustrate the technical solution of the present application, the following is a brief introduction to the drawings required for the technical description.

[0066] Figure 1 A flow chart of the VVER reactor type three-dimensional accident scenario data coupling analysis method provided in this application;

[0067] Figure 2 A flowchart for implementing the VVER reactor type three-dimensional accident scenario data coupling analysis method provided in this application;

[0068] Figure 3 A schematic diagram of the three-dimensional model of the VVER reactor provided in this application;

[0069] Figure 4A schematic diagram of the VVER stack dynamic effect provided by this application;

[0070] Figure 5 A schematic diagram of the important parameter monitoring interface provided by this application;

[0071] Figure 6 Data transmission flow chart provided for this application. DETAILED DESCRIPTION

[0072] The following is further explained in detail through specific implementation methods.

[0073] like Figure 1 and Figure 2 As shown, the present application discloses a VVER reactor type three-dimensional accident scenario data coupling analysis method, comprising the following steps:

[0074] Step 1: Based on the structural characteristics of the VVER reactor, the UNITY 3D engine platform is used to build a three-dimensional visualization model of the VVER reactor primary circuit, pressure vessel, pressurizer, steam generator, containment, and spent fuel pool;

[0075] Step 2: Create three-dimensional dynamic effects of each device in normal state and accident situation;

[0076] Step 3: Create important parameter monitoring interfaces for monitoring VVER reactor type severe accidents and online scenarios, including Shapiro diagram interface, parameter curve interface, main parameter interface, core parameter interface, off-site dose distribution interface, message output interface, containment parameter interface, spent pool parameter interface, and online scenario monitoring interface;

[0077] Step 4: Build the underlying database, including internal and external data;

[0078] Step 5: Construct a mapping point table between the underlying data and the VVER type three-dimensional accident / online scene front-end display interface, use the underlying data of severe accidents stored in the Redis database and the online real-time data as driving data, and combine the data communication interface to realize the mapping of data collection and point file correspondence on Redis;

[0079] Step 6: Dynamically display the three-dimensional accident process and real-time online process.

[0080] In some embodiments, Figure 3 As shown, step 1 specifically includes:

[0081] Step 1.1: Make a three-dimensional visualization model of the primary circuit, including the primary circuit pipeline, 1# steam generator SG1, 2# steam generator SG2, 3# steam generator SG3, 4# steam generator SG4, stabilizer, pressure vessel, and main pump;

[0082] Step 1.2: Make a three-dimensional visualization model of the pressure vessel, including the pressure vessel body, the reactor cavity, and the connected pipes;

[0083] Step 1.3: Make a three-dimensional visualization model of the pressure regulator, including the pressure regulator body, pressure relief pipeline and valve, and pressure relief box;

[0084] Step 1.4: Make a three-dimensional visualization model of the steam generator, including the steam generator body, feedwater pipelines (main feedwater and auxiliary feedwater pipelines) and valves, steam pipelines and valves;

[0085] Step 1.5: Make a three-dimensional visualization model of the containment, including the containment section, nuclear island auxiliary plant, refueling pool, spent fuel pool, spray system, primary circuit main equipment and pipelines, ring hanger, lighting, core melt catcher and its cooling facilities;

[0086] Step 1.6: Create a 3D visualization model of the spent fuel pool, including the spent fuel pool, wall, fuel assembly, ring hanger, and lighting.

[0087] In some embodiments, Figure 4 As shown, step 2 specifically includes:

[0088] Step 2.1: Create dynamic effects of pressure and temperature changes in the primary circuit system;

[0089] Step 2.2: Create dynamic effects of volumetric equipment such as steam generators, pressure vessels, pressurizers, pressure relief tanks, and working fluid loading in the spent fuel pool;

[0090] Step 2.3: Create dynamic flow effects of water and air inside the pipe;

[0091] Step 2.4: Create dynamic effects of bubbles inside the pipe;

[0092] Step 2.5: Make the dynamic effects of bubble generation, rise, expansion, and burst during the heating process of steam generators, pressure vessels, pressurizers, pressure relief boxes and other heat exchange equipment and spent fuel pools, as well as the internal steam flow;

[0093] Step 2.6: Create dynamic effects of pipeline rupture and fluid spraying;

[0094] Step 2.7: Create dynamic effects of the rupture of the steam generator heat transfer tube and the spraying of working fluid;

[0095] Step 2.8: Create dynamic effects of main steam pipe rupture and working fluid spraying;

[0096] Step 2.9: Create the dynamic effect of the pressure relief valve of the pressure regulator to release the working fluid;

[0097] Step 2.10: Create the dynamic effect of the spent fuel pool breach and fluid spraying;

[0098] Step 2.11: Create dynamic effects of core changes;

[0099] Step 2.12: Create dynamic effects of core heating, melting, melt flow, core collapse, melt entering the lower head, melt accumulation in the lower head, lower head heating, failure, melt entering the core catcher and reacting with the fillings therein;

[0100] Step 2.13: Make a dynamic effect of the core catcher to collect the core melt;

[0101] Step 2.14: Create dynamic effects of spent fuel heating, melting, melt flow, collapse, melt falling to the bottom of the spent fuel pool, melt accumulation at the bottom of the spent fuel pool, and heating of the bottom of the spent fuel pool;

[0102] Step 2.15: Create dynamic effects of changes in pressure, temperature, radioactivity, and hydrogen concentration in the containment under accident conditions;

[0103] Step 2.16: Create dynamic effects of steam in the containment;

[0104] Step 2.17: Create a dynamic effect of containment spraying on the containment;

[0105] Step 2.18: Create a dynamic effect of the pit water level change.

[0106] In some embodiments, Figure 5 As shown, step 3 specifically includes:

[0107] Step 3.1: Create a Shapiro diagram interface to display the changes in the content of air, combustible gas (mainly hydrogen and carbon monoxide), and inert gas (mainly steam and carbon dioxide) in the containment, so as to monitor hydrogen explosion, hydrogen combustion, and critical concentration in the containment;

[0108] Step 3.2: Create a parameter curve interface to display a curve chart of key parameters changing with time, covering various equipment such as containment, primary circuit, secondary circuit, such as containment temperature, pressure vessel water level, loop1 cold section water temperature, loop1 hot section water temperature, steam generator liquid level, etc., and you can freely select and switch the parameters you want to view in the drop-down menu; you can view the corresponding time, the corresponding parameter value, and zoom in and out the curve;

[0109] Step 3.3: Create a main parameter interface to display the main parameter values ​​changing over time. It consists of six parts: core parameters, pressure vessel, containment, primary circuit, secondary circuit, and other parameters. Each part includes the Chinese name, value, and unit of the parameter.

[0110] Step 3.4: Make the core parameter interface; Core parameter 2D interface: Display the core fuel temperature and fuel mass values ​​changing with time, where white numbers represent fuel temperature and black numbers represent fuel mass. The core nodes are divided into axial and radial, with 29 layers in the axial direction and 8 circles in the radial direction. The color of each node changes with the temperature color card. The nodes with high temperature are red, and the nodes with low temperature are blue. Gray indicates that the structure has melted and disappeared. Click the layer button on the right to enter the target layer core node interface and view the node parameter distribution of each layer; Core temperature parameter 3D interface: Display the three-dimensional interface of the core node. Click the layer to view the internal core temperature distribution. Gray indicates that the structure has melted and disappeared;

[0111] Step 3.5: Create an off-site dose distribution interface, which can display the depth dose rate, internal effective dose rate, and total effective dose rate values ​​at 1km, 5km, 10km, and 50km off-site over time, and display them dynamically with color gradients; it is convenient to distinguish off-site safe areas, hidden areas, and evacuation areas, and facilitate the rapid formulation of personnel evacuation plans in the event of an accident;

[0112] Step 3.6: Create a message output interface to display the key events and corresponding times that occurred during the accident process;

[0113] Step 3.7: Create the containment parameter interface. The containment parameters are divided into 10 areas, namely, the reactor pit, the lower compartment, the upper large space, the annular space, the refueling pool, the upper part of the auxiliary plant, the lower part of the auxiliary plant, the control room, the fuel loading and unloading area, and the spent fuel pool; the pressure, temperature, water level, hydrogen concentration, and radioactivity values ​​of each area are displayed over time; the color of each area changes with the temperature color card, the high temperature area is red, and the low temperature area is blue;

[0114] Step 3.8: Create the exhaust pool parameter interface; exhaust pool parameters Figure 2 D interface: The spent fuel pool is divided into 29 channels, with 22 layers in the axial direction, showing the spent fuel temperature value of each channel node changing with time. Click the layer button on the right to enter the spent fuel pool channel node interface of the target layer to view the temperature distribution of the channel nodes of each layer. The spent fuel pool level, spent fuel pool plant pressure, spent fuel pool plant temperature, spent fuel pool plant hydrogen concentration, spent fuel pool plant radioactivity value changing with time are displayed at the bottom of the interface to achieve real-time monitoring of the spent fuel pool; spent fuel pool parameters Figure 3 D interface: displays the three-dimensional spent fuel pool nodes; click on the layer to view the internal spent fuel temperature distribution;

[0115] Step 3.9: Create an online scene monitoring interface to display the numerical changes of important parameters of equipment structures such as primary circuit, pressure vessel, pressurizer, steam generator, containment, spent fuel pool, etc. in the online scene, such as spent fuel pool temperature, steam generator liquid level, pressure, feed water flow, pressurizer water level, temperature, core outlet temperature, containment temperature, hydrogen concentration, pump feed water flow, and dynamic numerical changes of parameters such as water temperature and flow of each circuit. In some embodiments, such as Figure 6 As shown, step 4 specifically includes:

[0116] Step 4.1: Internal data: The static accident scenario data calculated by the integrated severe accident analysis program is stored in the Redis database, mainly including: severe accidents initiated by small / medium / large ruptures in the hot pipe section, severe accidents initiated by small / medium / large ruptures in the cold pipe section, severe accidents initiated by ruptures in the main steam pipeline, severe accidents initiated by single / multiple steam generators, ruptures of heat transfer tubes, severe accidents initiated by loss of main feed water, severe accidents initiated by loss of water in the spent fuel pool, and severe accidents initiated by power outages in the entire plant, a total of 13 types of accident scenario data;

[0117] Step 4.2: External data: Store the external data in the Redis database. The external data communication interface communicates through the network. The data source is the real-time online data from the power plant.

[0118] Step 4.3: When sending data, the 3D program will use the conversion relationship in the configuration file to convert the Chinese name of the variable into the variable name, and convert the data into structured data and send it to the external database; when receiving data, the received structured data will be converted into the corresponding variable value and stored in the Redis database.

[0119] In some embodiments, Figure 6 As shown, step 5 specifically includes:

[0120] Step 5.1: Use the Config.json file to configure the system data type, data file location, database IP, port, scene and effect, and data name, point name, unit, etc. of all pages; configuration in the form of json is easy for operators to read and write, and is also easy for machines to parse and generate, and effectively improves network transmission efficiency, and has the function of simple calculation and the function of calculating the values ​​of multiple variables before taking values;

[0121] Step 5.2: Use the MessageStruct.txt file to configure the point table of the three-dimensional dynamic effect, Shapiro diagram interface, parameter curve interface, main parameter interface, core parameter interface, off-site dose distribution interface, message output interface, containment parameter interface, spent pool parameter interface, and online scene monitoring interface. The data communication interface provides the correspondence between the system and database point names; use the conversion relationship in the configuration file to convert the Chinese name of the variable into the variable name, and then find the corresponding key-value pair in the underlying static data to realize fast reading of the data.

[0122] In some embodiments, Figure 6 As shown, step 6 specifically includes:

[0123] Step 6.1: Sort out the simulation calculation parameters, extract the parameters required for the 3D model, and perform preprocessing according to the display requirements, such as merging calculations, normalization, unit conversion, etc.;

[0124] Step 6.2: Link the internal accident sequence scenario data with the 3D display models of related equipment, pipelines, flow media, etc. in the 3D scene, as well as the Shapiro diagram interface, parameter curve interface, main parameter interface, core parameter interface, off-site dose distribution interface, message output interface, containment parameter interface, and spent pool parameter interface;

[0125] Step 6.3: Link the external real-time online data with the 3D display models of the relevant equipment, pipelines, flowing media, etc. in the 3D scene, as well as the online scene monitoring interface;

[0126] Step 6.4: The driving screen displays 13 typical severe accident scenarios of the VVER reactor type, and displays in real time the status and phenomena of key equipment or systems of the nuclear power plant during severe accidents, including water vapor, water flow, bubbles, equipment liquid level changes, core meltdown, core catcher collecting molten material, breach spraying, containment spraying, pit liquid level, spent fuel meltdown and other effects, as well as dynamic changes in monitoring interfaces such as Shapiro diagram interface, parameter curve interface, main parameter interface, core parameter interface, off-site dose distribution interface, message output interface, containment parameter interface, and spent pool parameter interface;

[0127] Step 6.5: The driving screen displays the real-time online scene of the VVER reactor type, and displays in real time the status and phenomena of the key equipment or systems of the nuclear power plant in the online scene, including effects such as water vapor, water flow, bubbles, equipment liquid level changes, and dynamic changes of related important monitoring interfaces, as well as the online scene monitoring interface.

[0128] This application couples simulation data with 3D model data through a data communication module, and stores data in a Redis database in offline / online mode. The configuration file is combined with the database to manage and update data and configuration files. The file contains the conversion relationship between the system point table and the communication data.

[0129] There are two types of communication interfaces:

[0130] (1) Data communication interface for internal database data

[0131] The data communication interface of the internal database data is realized through the conversion relationship in the configuration file. In the case of static data, the static accident scene data calculated by the integrated serious accident analysis program is stored in the Redis database. The three-dimensional program will use the conversion relationship in the configuration file to convert the Chinese name of the variable into the variable name, and then find the corresponding key-value pair in the underlying static data to realize fast reading of the data.

[0132] The data required to drive the typical nuclear accident scenarios in the 3D display screen is provided by the preset internal Redis database. The typical accident sequence scenario data is calculated and generated by the severe accident calculation model based on the VVER reactor type. The typical severe accident scenarios include the models of the following scenarios:

[0133] 1) A serious accident occurred due to a small rupture in the heat pipe section;

[0134] 2) A small rupture in the cold pipe section caused a serious accident;

[0135] 3) Serious accidents caused by ruptures in the heat pipe section;

[0136] 4) Serious accidents caused by ruptures in the cold pipe section;

[0137] 5) Serious accidents caused by large ruptures in the heat pipe section;

[0138] 6) Serious accidents caused by large ruptures in the cold pipe section;

[0139] 7) Serious accidents caused by rupture of the main steam pipeline;

[0140] 8) A serious accident occurred due to the rupture of a single steam generator heat transfer tube;

[0141] 9) Multiple steam generator heat transfer tubes ruptured, causing a serious accident;

[0142] 10) Loss of main water supply may cause serious accidents;

[0143] 11) Severe accident of loss of water in spent fuel pool;

[0144] 12) A serious accident occurred due to power outage in the entire factory.

[0145] When the three-dimensional display screen needs to display the accident scene of a typical accident, the three-dimensional module will directly call the existing accident process data of the corresponding accident scene from the static data.

[0146] (2) Data communication interface of external database

[0147] The data communication interface of the external database needs to communicate through the network. In the implementation process, socket programming is used to send and receive data. When sending data, the 3D program will use the conversion relationship in the configuration file to convert the Chinese name of the variable into the variable name, and convert the data into structured data and send it to the external database. When receiving data, the program converts the received structured data into the corresponding variable value and stores it in the Redis database.

[0148] At the same time, it provides an external text data interface. The source of external text data can be real-time data from power plants or data generated by real-time simulation of severe accident calculation models. External data is stored in the Redis database, and its visual interface is easy to operate and modify. It realizes business logic data storage, historical data storage functions, historical data query, playback and other functions, including historical data trend function query, etc.

[0149] In summary, the method provided in the present application establishes a three-dimensional visualization model of the primary circuit, pressure vessel, pressurizer, steam generator, containment, and spent fuel pool of the VVER reactor type according to the structure and design characteristics of the VVER reactor type, and produces three-dimensional dynamic effects of each device in normal state and accident conditions on the basis of the three-dimensional model, as well as an important parameter monitoring interface for monitoring the VVER reactor type severe accident / online scenarios, and constructs an underlying database driven by its corresponding parameters. The data is parsed, reproduced, and reconstructed through a special data interaction program and a configuration point table, realizing the coupling and linkage of typical accident sequence scenario data with the three-dimensional simulation model, driving the typical nuclear accident scenario in the 3D display screen, and at the same time, the three-dimensional accident scene display can support covering various typical severe accident scenarios, and has the ability to access real-time real scene data on the power plant side, and dynamically display the development process online.

[0150] This application uses an integrated accident simulation program to simulate and calculate 12 typical accident scenarios, including large / medium / small ruptures in cold pipe sections, large / medium / small ruptures in hot pipe sections, power outages in the entire plant, ruptures in single / multiple heat transfer pipes of steam generators, ruptures in main steam pipes, loss of main feed water, and water loss in spent fuel pools, as internal data. Create an external general data coupling interface, access real-time data from the power plant side as external data, store internal and external data in the Redis database, and realize the construction of the underlying database. In the form of point tables, data is coupled with dynamic special effects and data monitoring modules to drive the screen to display typical severe accidents / online scenarios of VVER reactors. In severe accident scenarios, the status and phenomena of key equipment or systems in nuclear power plants during severe accidents can be displayed, including water vapor, water flow, bubbles, equipment level changes, core meltdown, core catcher collecting molten material, breach spraying, containment spraying, pit level, spent fuel meltdown and other effects. At the same time, you can choose to enter the Shapiro diagram, parameter curve, main parameters, core parameters, off-site dose distribution, message output, containment parameters, spent pool parameter diagram and other interfaces to query related parameters. In online scenarios, the status and phenomena of key equipment or systems in online nuclear power plants on the power plant side are displayed, including water vapor, water flow, bubbles, equipment level changes and other effects. At the same time, you can enter the online scenario monitoring interface to query related parameters and display the development process in the online scenario.

[0151] The above description is only a specific implementation manner of the present application, but the protection scope of the present application is not limited thereto. Any changes or substitutions that can be easily conceived by any technician familiar with the technical field within the technical scope disclosed in the present application should be covered within the protection scope of the present application.

Claims

1. A method for coupling analysis of VVER reactor type three-dimensional accident scenario data, characterized in that: include: Step 1: Based on the structural characteristics of the VVER reactor, a three-dimensional visualization model of the VVER reactor primary loop, pressure vessel, pressurizer, steam generator, containment, and spent fuel pool is constructed; Step 2: Create three-dimensional dynamic effects of the VVER reactor primary loop, pressure vessel, pressurizer, steam generator, containment, and spent fuel pool in normal and accident conditions; Step 3: Create an important parameter monitoring interface for monitoring VVER reactor type severe accidents and online scenarios; Step 4: Build the underlying database, including internal and external data; Step 5: Construct a mapping point table between the underlying data and the VVER type three-dimensional accident and the online scene front-end display interface. Use the underlying data of severe accidents stored in the Redis database and the online real-time data as driving data, and combine the data communication interface to realize the mapping of data collection and point file correspondence on Redis. Step 6: Dynamically display the three-dimensional accident process and real-time online process.

2. The VVER reactor type three-dimensional accident scenario data coupling analysis method according to claim 1 is characterized in that: Step 1 specifically includes: Step 1.1: Make a three-dimensional visualization model of the primary circuit, including the primary circuit pipeline, 1# steam generator SG1, 2# steam generator SG2, 3# steam generator SG3, 4# steam generator SG4, stabilizer, pressure vessel, and main pump; Step 1.2: Make a three-dimensional visualization model of the pressure vessel, including the pressure vessel body, the reactor cavity, and the connected pipes; Step 1.3: Make a three-dimensional visualization model of the pressure regulator, including the pressure regulator body, pressure relief pipeline and valve, and pressure relief box; Step 1.4: Make a 3D visualization model of the steam generator, including the steam generator body, feedwater pipeline and valve, steam pipeline and valve; Step 1.5: Make a three-dimensional visualization model of the containment, including the containment section, nuclear island auxiliary plant, refueling pool, spent fuel pool, spray system, primary circuit main equipment and pipelines, ring hanger, lighting, core melt catcher and its cooling facilities; Step 1.6: Create a 3D visualization model of the spent fuel pool, including the spent fuel pool, wall, fuel assembly, ring hanger, and lighting.

3. The VVER reactor type three-dimensional accident scenario data coupling analysis method according to claim 1 is characterized in that: Step 2 specifically includes: Step 2.1: Create dynamic effects of pressure and temperature changes in the primary circuit system; Step 2.2: Create dynamic effects of the volumetric equipment and the working fluid loading in the spent fuel pool; Step 2.3: Create dynamic flow effects of water and air inside the pipe; Step 2.4: Create dynamic effects of bubbles inside the pipe; Step 2.5: Create dynamic effects of heat exchange equipment and internal steam flow; Step 2.6: Create dynamic effects of pipeline rupture and fluid spraying; Step 2.7: Create dynamic effects of the rupture of the steam generator heat transfer tube and the spraying of working fluid; Step 2.8: Create dynamic effects of main steam pipe rupture and working fluid spraying; Step 2.9: Create the dynamic effect of the pressure relief valve of the pressure regulator to release the working fluid; Step 2.10: Create the dynamic effect of the spent fuel pool breach and fluid spraying; Step 2.11: Create dynamic effects of core changes; Step 2.12: Create dynamic effects of core heating, melting, melt flow, core collapse, melt entering the lower head, melt accumulation in the lower head, lower head heating, failure, melt entering the core catcher and reacting with the fillings therein; Step 2.13: Make a dynamic effect of the core catcher to collect the core melt; Step 2.14: Create dynamic effects of spent fuel heating, melting, melt flow, collapse, melt falling to the bottom of the spent fuel pool, melt accumulation at the bottom of the spent fuel pool, and heating of the bottom of the spent fuel pool; Step 2.15: Create dynamic effects of changes in pressure, temperature, radioactivity, and hydrogen concentration in the containment under accident conditions; Step 2.16: Create dynamic effects of steam in the containment; Step 2.17: Create a dynamic effect of containment spraying on the containment; Step 2.18: Create a dynamic effect of the pit water level change.

4. The VVER reactor type three-dimensional accident scenario data coupling analysis method according to claim 1 is characterized in that: Step 3 specifically includes: Step 3.1: Create a Shapiro diagram interface to display the changes in the content of air, combustible gas, and inert gas in the containment; Step 3.2: Create a parameter curve interface to display the curve graph of key parameters changing over time; Step 3.3: Create a main parameter interface to display the changes of main parameter values ​​over time; Step 3.4: Create a core parameter interface, including a core parameter 2D interface and a core temperature parameter 3D interface; Step 3.5: Create an off-site dose distribution interface to display the off-site depth dose rate, internal effective dose rate, and total effective dose rate values ​​changing over time; Step 3.6: Create a message output interface to display the key events and corresponding times that occurred during the accident process; Step 3.7: Create the containment parameter interface, including the reactor pit, lower compartment, upper large space, annular space, refueling pool, upper auxiliary building, lower auxiliary building, control room, fuel loading and unloading area, and spent fuel pool; Step 3.8: Create a spent pool parameter interface, including a spent pool parameter diagram 2D ​​interface and a spent pool parameter diagram 3D interface; Step 3.9: Create an online scene monitoring interface to display the dynamic changes in the numerical values ​​of the parameters covering the equipment structure in the online scene.

5. The VVER reactor type three-dimensional accident scenario data coupling analysis method according to claim 4 is characterized in that: In step 3.2, the key parameters are those of the primary loop, pressure vessel, pressurizer, steam generator, containment, and spent fuel pool, including containment temperature, pressure vessel water level, loop1 cold section water temperature, loop1 hot section water temperature, and steam generator liquid level.

6. The VVER reactor type three-dimensional accident scenario data coupling analysis method according to claim 4 is characterized in that: In step 3.3, the main parameters are those of the primary circuit, pressure vessel, pressurizer, steam generator, containment, and spent fuel pool, including the maximum core temperature, power, pressure vessel top pressure, gas concentrations in the containment, primary circuit water temperature, steam generator secondary side pressure, and pressurizer spray flow.

7. The VVER reactor type three-dimensional accident scenario data coupling analysis method according to claim 4 is characterized in that: In step 3.4, the core parameter 2D interface is used to display the changes of core fuel temperature and fuel mass values ​​over time, and the core temperature parameter 3D interface is used to display the three-dimensional interface of the core node.

8. The VVER reactor type three-dimensional accident scenario data coupling analysis method according to claim 1 is characterized in that: Step 4 specifically includes: Step 4.1: Store the static accident scenario data calculated by the integrated severe accident analysis program in the Redis database; Step 4.2: Store external data in the Redis database, and the external data communication interface communicates through the network; Step 4.3: When sending data, the conversion relationship in the configuration file will be used to convert the Chinese name of the variable into the variable name, and the data will be converted into structured data and sent to the external database; when receiving data, the received structured data will be converted into the corresponding variable value and stored in the Redis database.

9. The VVER reactor type three-dimensional accident scenario data coupling analysis method according to claim 1 is characterized in that: Step 5 specifically includes: Step 5.1: Configure the data type, data file location, database IP, port, scene and effect, and data name, point name, and unit of all pages; Step 5.2: Configure the point table. The data communication interface provides the correspondence between the front-end three-dimensional dynamic effects, Shapiro diagram interface, parameter curve interface, main parameter interface, core parameter interface, off-site dose distribution interface, message output interface, containment parameter interface, spent pool parameter interface, and online scene monitoring interface and the underlying database point names; use the conversion relationship in the configuration file to convert the Chinese name of the variable into the variable name, and then find the corresponding key-value pair in the underlying static data to realize fast reading of data.

10. The VVER reactor type three-dimensional accident scenario data coupling analysis method according to claim 1 is characterized in that: Step 6 specifically includes: Step 6.1: Sort out the simulation calculation parameters, extract the parameters required for the 3D model, and pre-process according to the display requirements; Step 6.2: Link the internal accident sequence scene data, the 3D display model of the 3D scene, the Shapiro diagram interface, the parameter curve interface, the main parameter interface, the core parameter interface, the off-site dose distribution interface, the message output interface, the containment parameter interface, and the spent pool parameter interface; Step 6.3: Linking external real-time online data, the three-dimensional display model of the picture in the three-dimensional scene, and the online scene monitoring interface; Step 6.4: The driving screen displays the severe accident scenario and real-time online scenario of the VVER reactor type, and displays the status and phenomena in the key equipment or system of the nuclear power plant during severe accidents and real-time online.

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