3844 results about "Nuclear power" patented technology

The invention relates to the technical field of frequency conversion control, and discloses a frequency conversion control method and system for a nuclear power station ventilation system, and the method comprises the steps: collecting the multi-region real-time operation data of the nuclear power station ventilation system, and carrying out the standardization processing, and obtaining a standardized data set; performing fan performance curve fitting and differential pressure field feature mapping on the standardized data set to obtain differential pressure field mapping features; the differential pressure field mapping features are input into an active neural differential pressure field network model for frequency conversion parameter prediction, and target frequency conversion control parameters are obtained; feedforward-feedback combined control is conducted on the target frequency conversion control parameters through the multi-mode frequency conversion controller, the fan rotating speed and the air valve opening value are obtained, the target frequency conversion control parameters can be generated in a self-adaptive mode, the control performance is remarkably improved, and smooth transition of the nuclear power station ventilation system is achieved.

The invention relates to the technical field of nuclear power internal disaster analysis, and discloses a nuclear power plant internal flooding experiment verification method, device, equipment and medium, and the method comprises the steps: carrying out the modeling analysis of a target plant prototype, and determining a plurality of model parameter values of an experiment scaling model; constructing an experiment scaling model according to the plurality of model parameter values, and determining experiment parameters of an internal water logging experiment; performing an internal water logging experiment on the experimental scale model by using the experimental parameters to obtain an internal water logging experiment result of the experimental scale model; and obtaining an internal water logging simulation result of the numerical model, comparing the internal water logging simulation result with an internal water logging experiment result, and verifying the accuracy of the internal water logging simulation result according to a comparison result. According to the method, the experiment scale model of the nuclear power plant prototype is constructed, the flooding spreading conditions under different working conditions are simulated and compared with the flooding simulation result, the accuracy of flooding simulation calculation is verified, and more accurate guidance is provided for follow-up nuclear power project internal flooding analysis.

The invention provides an AI-based nuclear power station high-risk operation compliance real-time monitoring method and system, and the method comprises the steps: processing human body joint point coordinate data of an operator through employing an AI dynamic contour modeling algorithm, and generating a limb movement track sequence; scanning the preset operation area to generate a relative motion vector between the special operation tool for the nuclear power station and the operator; detecting an action deviation mode of the operator based on the limb movement track sequence, and generating a detection result; fusing the relative motion vector and multi-channel video stream frame synchronization data obtained by applying an AI video analysis algorithm to generate a space intrusion relation between the nuclear power station special operation tool and the nuclear power station high-risk equipment; and when the action deviation mode exists in the detection result and the space intrusion relation exceeds a preset safety threshold, generating an operation compliance signal. According to the invention, real-time dynamic evaluation of human motion compliance and tool equipment safety distance in the high-risk operation process of the nuclear power station is realized, and the safety monitoring precision and real-time early warning capability of high-risk operation are improved.

The invention relates to the technical field of computers, and discloses a nuclear power safety report examination method and system, electronic equipment and a storage medium, and the method comprises the steps: receiving an examination request, carrying out the intention recognition and entity extraction based on a nuclear power field large language model, and disassembling an examination task into a structured subtask sequence based on an intention type and an entity attribute; performing multi-modal retrieval based on the structured sub-task sequence, and outputting a multi-source retrieval result; calling time-space association information of the evolutionary knowledge graph, and outputting knowledge support data in combination with the time sequence model; fusing a multi-source retrieval result and the knowledge support data, performing risk value calculation and uncertainty quantification through a deep learning model, and outputting a risk assessment result; and based on the risk assessment result, carrying out federal learning model parameter adjustment, carrying out uplink evidence storage on the review conclusion, the risk assessment result and the evidence chain, and outputting the review result. The method has the advantages of being efficient, accurate, dynamic, safe and closed-loop during examination.

The invention relates to the technical field of nuclear power equipment quality management and control, in particular to a nuclear power unit quality defect source analysis and total value chain tracing method, which comprises the following steps: S01, collecting total value chain multi-modal data including structured data, logs, texts and sensor time sequence data, and carrying out BIO labeling, BERT coding, BiGRU-Attention feature extraction and CRF sequence labeling; constructing a mixed storage data resource pool; s02, mining association rules by adopting a dynamic pruning improved Apriori algorithm, processing sample imbalance in combination with chi-square test and an NSGAII algorithm, and analyzing defect causes; s03, a dynamic knowledge graph containing multiple types of nodes, relations and threshold attributes is constructed, and rapid defect tracing is achieved through entity linking and probability path searching; the objective of the invention is to solve the problems of difficulty in defect source calibration, low tracing efficiency and the like in nuclear power equipment quality control.

The invention relates to the field of nuclear power unit accident analysis, in particular to a coupling method of a VVER unit system program and a neutron dynamics program. The method comprises the following steps: adding an interface function in a reactor core three-dimensional neutron dynamics program, compiling the reactor core three-dimensional neutron dynamics program into a dynamic link library, and accessing and calling the dynamic link library by a reactor system program in a plug-in manner; establishing a neutronics physical model of a specific loading scheme of the VVER type reactor; establishing an accident analysis system simulation model of the VVER type pressurized water reactor; establishing control logic of main systems and equipment of a primary loop and a secondary loop in the VVER type reactor; establishing control logic and conservative condition settings for specific accidents; executing coupling calculation of a reactor system program and reactor core three-dimensional neutron dynamics; and obtaining key safety parameters of the VVER type reactor in a specific accident based on a coupling calculation result. According to the invention, simulation of changes of physical and thermal parameters in a primary loop system and a secondary loop system and action response of a main system after a reactor has an accident can be realized, and efficient and reliable accident analysis can be conveniently carried out on a VVER type nuclear power unit.

The invention relates to the technical field of machine learning and nuclear power safety assessment, and discloses a nuclear power safety assessment method and system based on machine learning, and the method comprises the steps: collecting and preprocessing the multi-source heterogeneous data of a nuclear power station; constructing a time convolution network model to extract multi-scale time sequence features of the multi-modal data and realize modal alignment; constructing a contrast learning model to optimize multi-modal feature representation; constructing a multi-granularity prototype learning model in the optimized feature representation space; constructing an adaptive attention fusion model to dynamically integrate multi-modal information, and continuously optimizing an evaluation model by a continuous learning technology; through multi-modal fusion and multi-scale time sequence representation learning, comprehensive assessment of the safety state of the nuclear power station is realized, and the comprehensiveness of safety assessment is improved.

The embodiment of the invention provides a nuclear power equipment operation health state monitoring method and system, electronic equipment and a storage medium, and belongs to the technical field of nuclear power. The method comprises the following steps: acquiring equipment temperature data, equipment pressure data and equipment structure information corresponding to target monitoring equipment; wherein the equipment structure information is pre-configured with a corresponding stress influence evaluation strategy; performing load stress analysis on the target monitoring equipment based on the equipment temperature data and the equipment pressure data to obtain load stress monitoring parameters corresponding to multiple load types; for the target monitoring equipment, processing the load stress monitoring parameters of various load types according to a stress influence evaluation strategy to obtain health influence parameters; and performing health state evaluation according to the health influence parameters to obtain health state characterization information corresponding to the target monitoring equipment. According to the embodiment of the invention, health state monitoring can be carried out on a complex nuclear power equipment structure.

The invention discloses a self-adaptive control method and system for a condenser for a nuclear power station, relates to the field of condenser control, and aims to predict a future load change trend in a prospective manner by analyzing historical data of a unit power instruction and steam flow, and calculate feed-forward circulating water flow based on a prediction result. On the basis, a feedback control loop based on actually measured pressure is reserved. More importantly, a self-adaptive bias correction mechanism is introduced, and continuous learning and correction are carried out on output of feedback control, so that steady-state errors of the system are eliminated, and uncertainty of the model is compensated. Finally, feed-forward, feedback and self-adaptive correction components are intelligently fused to form a final control instruction which can quickly respond to load changes and can accurately maintain pressure stability, and the problems of severe pressure fluctuation and energy waste under the dynamic working condition are effectively solved.

The invention discloses a fuel rod cladding surface corrosion product deposition test device and method, and belongs to the field of nuclear power. The fuel rod cladding surface corrosion product deposition test device comprises a water supply section and a test section, the test section comprises a high-pressure kettle and a cladding pipe contained in the high-pressure kettle, and a heater is arranged in the cladding pipe to simulate heating of a fuel rod; the water supply section is used for providing circulating solution for the test section and comprises a coolant water tank, a dirt source water tank, a heating device, a pump set and a circulating pipeline, the coolant water tank circularly intervenes in the circulating pipeline to provide circulating simulated coolant, the dirt source water tank is used for injecting simulated dirt liquid into the circulating pipeline, the pump set is used for providing driving force, and the heater is used for heating. The device can accurately control the hydrochemical conditions of the dirt deposition test, keeps the consistency and repeatability of the test conditions in the test process, effectively improves the simulation test precision, and optimizes the test efficiency.

The invention belongs to the field of metal material processing, and particularly relates to a nuclear power nickel base alloy welding wire and a preparation method thereof.The nuclear power nickel base alloy welding wire comprises, by weight, 0.01%-0.05% of C, 0.10%-0.30% of Si, 28.5%-30.5% of Cr, 7.0%-11.0% of Fe, smaller than or equal to 0.10% of Co, 0.50%-1.00% of W, 3.0%-4.0% of Mo, 0.005%-0.010% of B, 0.1%-0.3% of Al, 0.1%-0.2% of Ti, 0.005%-0.020% of Zr, 2.0%-2.5% of Nb, 0.1%-0.5% of Ta, 0.20%-0.30% of RE, smaller than 0.005% of S, smaller than 0.005% of P, 2.0%-4.0% of nano ceramic materials and the balance Ni, the nickel-based alloy welding material is prepared through the steps of smelting, high-low temperature refining, annealing, forging, rolling, multi-pass drawing, annealing, solid solution-aging treatment, acid pickling, coating and plating, and the problems that in the prior art, when used for welding, a nickel-based alloy welding material is prone to cracks, and the strength is low due to hot corrosion can be effectively solved.

The invention discloses a real-time judgment method for roof collapse caused by a fire between nuclear power station oil storage tanks, and relates to the technical field of fire safety design of roof structures between nuclear power station oil storage tanks. Acquiring time sequence temperature data of the grid nodes; establishing a three-dimensional heat conduction model of the roof structure; top plate structure heating surface temperature field mapping is realized; carrying out three-dimensional heat transfer simulation on the top plate structure; analyzing the instability critical condition of the roof structure. According to the real-time judgment method for the roof collapse caused by the fire between the oil storage tanks of the nuclear power station, time sequence temperature field mapping of the heated surface of a complex roof structure between CFD numerical simulation software and FEM software in different fire scenes between the oil storage tanks of the nuclear power station can be realized; real-time structure response behaviors of the nuclear power station oil storage tank roof structure in different fire scenes are simulated, and the method can be used for fire safety design and post-disaster damage evaluation of the nuclear power station oil storage tank roof structure.

The invention relates to a containment pressure suppression, filtration and discharge system and method and application thereof, and belongs to the field of special safety facilities and radiation protection of nuclear power devices. The containment pressure suppression, filtration and discharge system comprises a discharge valve (2), a discharge pipeline (3), a spray pipe (4), a pressure suppression pool, an expansion chamber (7), a steam-water separator (9), a metal fiber filter layer (10), a rupture disk (12), a heat exchanger and a valve. According to the containment pressure suppression filtering and discharging system, the seawater side heat exchanger and the pressure suppression pool heat exchanger are arranged, and a natural circulation loop is constructed by means of the potential difference between the seawater side heat exchanger and the pressure suppression pool heat exchanger and the temperature difference between seawater and a liquid phase in a pressure suppression pool under the accident condition; the heat of the suppression pool can be guided out without time limit under the condition of an LOCA accident or a main steam pipeline fracture accident in the containment; by adopting a pressure suppression washing method with multi-stage bubbling, rapid pressure suppression of the containment and efficient retention of airborne radioactive substances can be realized; occupation of total resources is reduced by arranging the combined metal fiber filter layer.

The invention particularly relates to a nuclear power important parameter abnormity identification and alarm system. The system comprises a data warehouse and at least one group of parameter abnormity identification modules arranged in the data warehouse. And each parameter abnormity identification module receives the real-time operation data of the unit as input so as to carry out abnormity identification and alarm on specified nuclear power parameters. According to the invention, the operation state of the unit is monitored, and the abnormity of important parameters, equipment and systems can be identified timely and accurately.

The invention belongs to the technical field of nuclear power, and particularly relates to a device and method for remote installation of a heat insulation sleeve relieving cushion block. Comprising a gripping apparatus and a screwing tool, the gripping apparatus is used for gripping the cushion block, the bolt and the locking cap to mount and dismount the cushion block, and the screwing tool is used for positioning and mounting the relieving cushion block on the upper cover plate of the control rod guide cylinder and fastening the bolt. The clamping device has the beneficial effects that the air cylinder is adopted to drive the grabhooks to be opened and closed, clamping of the cushion block is achieved, meanwhile, it is guaranteed that the grabhooks are in an open state during air loss through the built-in springs, and the cushion block is prevented from falling off. A grabbing structure that the bolts and the locking caps are lifted along with the cushion blocks is adopted, meanwhile, the anti-falling function is achieved, and integrated operation of clamping, conveying, positioning and screwing of the cushion blocks is achieved.

To provide a comparison method and a search method of strings to be optimized mainly focusing on Chinese search, based on a string search process of data information of a nuclear fuel management process.SOLUTION: These methods include steps of: splitting and preprocessing a target string and integrating a corresponding language library; calculating an editing distance and performing preliminary filtering using a character distance algorithm; and searching a Chinese string and verifying its collation degree using the Aho-Corasick algorithm, and caching frequently searched pattern strings after searching.SELECTED DRAWING: Figure 1

The invention discloses nuclear power large pipeline butt weld automatic welding equipment which is installed on a rail and comprises a walking assembly, the walking assembly comprises a walking driving piece, a walking driving wheel, two walking driven wheels and two walking shafts, the walking driving piece is in transmission connection with the walking driving wheel, and the walking driving wheel is in transmission connection with the walking driven wheels; the two walking driven wheels are in transmission connection with the two sides of the walking driving wheel respectively, each walking driven wheel is connected with one walking shaft, and at least one walking shaft is provided with walking wheel teeth meshed with the straight teeth on the track. A group of walking driven wheels are symmetrically arranged on the two sides of the walking driving wheel, so that the shaking phenomenon caused by the back clearance of the gear and the translation of the gravity center when equipment walks near the highest point or the lowest point of the track can be effectively prevented, the stability of the welding process is further ensured, and the welding quality can be better improved. And meanwhile, a driving mode of a single walking driving piece is adopted, control hardware and programs are simplified, and the production cost and the development time are reduced.

The invention relates to the technical field of safety monitoring of a nuclear reactor, and particularly discloses a multi-region pressure overrun leakage monitoring method for a reactor pressure vessel. The method comprises the steps of multi-region pressure data acquisition, real-time pressure field model construction, dynamic pressure field baseline modeling, pressure overrun anomaly detection, leakage source accurate positioning and evaluation based on spatial gradient analysis, topological structure mapping and multi-sensor data fusion, and graded early warning and response. By the adoption of the technical scheme, real-time and fine monitoring of pressure distribution in the reactor pressure vessel can be achieved, the rapid and accurate judgment and positioning capacity of leakage events is improved, the operation safety and reliability of nuclear power facilities are enhanced, and the reliability of the nuclear power facilities is improved. The defects of independent monitoring, local accurate positioning and complex working condition adaptability of multi-region pressure over-limit leakage in the prior art are overcome.

A long-term fuel management method based on accident-tolerant fuel, comprising the following steps: providing replacement fuel assemblies with a first enrichment degree, a second enrichment degree, and a third enrichment degree, wherein 5% < the first enrichment degree < the second enrichment degree < the third enrichment degree, and the replacement fuel assemblies adopt accident-tolerant fuel; taking out 69 groups of fuel assemblies in the reactor and putting them into the spent fuel pool, selecting a group of fuel assemblies with the highest reserve reactivity from the spent fuel pool and setting it at the center of the reactor, and taking 68 groups of replacement fuel assemblies and the remaining fuel assemblies in the reactor as a refueling group; calculating the installation sequence of the refueling group according to the reactor design limit and safety certification conditions and installing it; repeating refueling every 24 months. This method can extend the fuel cycle period to 24 months, effectively improve the fuel utilization rate, and improve the economy of nuclear power plants.

The invention discloses a building carbon emission habit analysis method, device and equipment and a storage medium, and relates to the technical field of electric digital data processing. According to the method, the total energy consumption, such as the power consumption and the fuel combustion amount, of the building is obtained from resource purchasing which is easy to inquire, the total energy consumption, such as the power consumption and the fuel combustion amount, of the building can be obtained simply, and then each energy consumption device is separated to a thermal power station and a nuclear power station and to household appliances, cooking benches and the like of a residential building. The linear relation between the starting-up duration and the total carbon emission of each device is analyzed through linear regression, meanwhile, the size of a linear regression coefficient reflects the carbon emission of the device in unit time, and the larger the linear regression coefficient is, the larger the carbon emission of the device in unit time is. The carbon emission per unit time of each device can also be obtained from linear regression, and necessary data support is provided for the fields of subsequent large-scale carbon emission research and the like.

The invention belongs to the field of ferrous metal materials, and particularly relates to a high-strength heat-resistant ferritic stainless steel plate for a third-generation nuclear power plant and a manufacturing method of the high-strength heat-resistant ferritic stainless steel plate for the third-generation nuclear power plant, and the high-strength heat-resistant ferritic stainless steel plate comprises the following chemical components in percentage by weight: 0.01%-0.12% of C, 0.8%-1.5% of Si, 0.02%-0.70% of Mn, 0.020%-0.050% of S, 0.01%-1.2% of Ni, 12.5%-14.5% of Cr, 0.2%-0.9% of Mo, 0.001%-0.010% of Zr, 0.010%-0.020% of Mg, 5-15 ppm of Ce, 0.00032%-0.003% of Ca and the balance of Fe. And the balance of Fe and inevitable impurities. The product produced according to the chemical components and production process requirements of the steel disclosed by the invention has high strength and toughness, low hardness and high temperature resistance.

The invention discloses a valve with an ultra-erosion-resistant function for a nuclear power plant, and relates to the technical field of valves. Through cooperation of the driving motor, the threaded rod, the threaded cylinder and the valve plate, lifting of the valve plate is accurately controlled conveniently, and the function of accurately adjusting the flow of the valve is achieved; the sealing performance of the valve element and the valve port is monitored through the analysis module, sealing hidden dangers can be found in time, medium leakage caused by the sealing problem is avoided, the sealing reliability of the valve is effectively improved, and the defect that the sealing problem is prone to occurring due to rigid abutting connection of the valve element and the valve port of a traditional valve is overcome. By comprehensively considering the pressure of the valve core and the valve port, the number of impurity particles, the particle size, the hardness, the medium flow rate, the impact angle and other factors, the calculation of the abrasion loss is more accurate, and the abrasion condition of the nuclear power plant valve in actual operation can be more accurately reflected.

The invention belongs to the field of nuclear power stations, and particularly relates to a reactor measuring coil sectional type rod position detector and a measuring method thereof, the detector comprises a measuring coil, a temperature compensation coil, a temperature compensation coil support groove and a coil holder; the measuring coil is wound on the coil holder, a temperature compensation coil supporting groove is formed in the coil holder, and the temperature compensation coil is wound in the temperature compensation coil supporting groove; the measuring coil is divided into N sections, and N is an integer greater than or equal to 2; each section of measuring coil is a continuous coil, and the N sections of measuring coils have no overlapped part. According to the invention, the rod position measurement precision, the rod position measurement reliability and the rod position measurement applicability can be greatly improved.

The invention relates to a detection method and application of a bainite steel structure and / or grain boundary for nuclear power equipment, and relates to the technical field of new material detection. According to the detection method, the problem that the structure and the grain boundary of bainite steel for nuclear power equipment are difficult to display can be solved, a major breakthrough of a grain size detection technology is achieved, the clear and complete grain boundary can be accurately presented, and scientific evaluation of the grain size through a comparison method, a cut point method, an area method and the like according to standard requirements is further supported. When the detection method is used for evaluating the grain size, the results are highly consistent, the repeatability is good, and the problems of subjective experience dependence and measurement errors caused by blurred grain boundary display in a traditional nitric acid and alcohol corrosion method are effectively avoided.

The invention discloses a dredging method of a robot for a nuclear power seawater pump room, the robot, a storage medium and a program product, and the method comprises the steps: receiving a task instruction corresponding to a dredging task of the nuclear power seawater pump room, and collecting environment image data through an image collection device arranged on the robot, environmental sonar data are collected through a sonar sensor; according to the task instruction, the environment image data, the environment sonar data and a task planning model, determining a plurality of sub-tasks and environment feature data corresponding to the dredging task; and determining associated feature data according to the plurality of sub-tasks, the environment feature data and a feature fusion model, and determining a target dredging path corresponding to the dredging task according to the associated feature data, a preset constraint condition of the robot and a path planning model. According to the technical scheme, the safety, efficiency and intelligent level of the dredging operation of the robot in the nuclear power seawater pump room can be effectively improved.

The invention discloses a three-dimensional modeling and intelligent operation and maintenance system and method for a nuclear power plant, and the system comprises a design drawing marking module which is used for carrying out the digital processing of a design drawing of the nuclear power plant; the data acquisition module is used for acquiring multi-dimensional data from a plurality of business systems of the nuclear power plant; the data processing module is used for carrying out data cleaning, conversion and standardization processing on the annotation file and the collected multi-dimensional data; the engineering integrated database is used for storing structured geometric information and multi-dimensional engineering data; the three-dimensional modeling module is used for generating a three-dimensional digital model based on the structured data; the real-time data updating module is used for dynamically updating the equipment state, the fault information and the position relation in the three-dimensional digital model; the three-dimensional visual display module is used for displaying the equipment layout, the pipeline trend and the building structure of the nuclear power plant; and the intelligent operation and maintenance module is used for equipment fault prediction. According to the invention, intelligentization and high efficiency of full-life-cycle management of the nuclear power plant are promoted.

The invention discloses a nuclear power plant reactor core optimization power control method based on imitation learning. A reactor core optimization power control model comprising a plurality of intelligent agents and an average layer is constructed based on the imitation learning method; and averaging the output results of the trained agents as a final control result. According to the invention, nuclear power plant reactor core optimization power control is developed based on an imitation learning method, an intelligent agent is trained in a supervised manner to learn a nuclear power plant power control system and decision logic of an operator, and serious consequences caused by direct interaction between an immature intelligent agent and a power plant are avoided while real data of the power plant are effectively utilized. A plurality of agents are integrated by adopting an integrated learning method, so that the model can be suitable for multiple working conditions of peak regulation, normal start-stop and emergency shut-down of a plurality of nuclear power plants. Each agent is optimized based on the Bayesian method in the training process, the optimal hyper-parameter is searched, and the network training efficiency and the fault diagnosis precision are improved.

The present application relates to a method and system for filling water in a primary loop after overhaul charging of a nuclear power unit, comprising: performing preparation work before filling water; after the preparation work is completed, performing switch operation test of a to-be-tested actuator and water filling and exhaust work of a flowmeter; after the switch operation test of the to-be-tested actuator is completed, performing performance test of a high-pressure safety injection pump; after the performance test of the high-pressure safety injection pump is completed, performing performance test of a low-pressure safety injection pump; after the performance test of the low-pressure safety injection pump is completed, filling water in the primary loop according to a preset water filling mode; judging whether a real-time water level of a reactor pool reaches a full water level; if yes, performing alarm action test. The present application can solve the problem of long time consumption, reduce workload, significantly improve work efficiency, reduce work risk and effectively save production cost by completing the preparation work in advance and arranging the alarm action test at the end.

The invention discloses a creep fatigue state evaluation method and system for high-temperature nuclear power station equipment. The method comprises the following steps: acquiring operation state parameter data of the high-temperature nuclear power station equipment; determining a total strain range of the equipment based on the operation state parameter data; according to the total strain range, the allowable cycle index and the creep initial stress of the equipment are determined; determining the fatigue damage and the creep damage of the equipment by using the allowable cycle index and the creep initial stress respectively; and based on the fatigue damage and the creep damage, evaluating the creep fatigue state of the equipment. Creep-fatigue comprehensive damage full-period safety and service life analysis management of key components of the high-temperature power station can be realized, when equipment has risks, an evaluation result is fed back to a main control room in time to remind a user of focusing on attention and monitoring, and a corresponding technical scheme is provided for a health monitoring and service life prediction system of a digital nuclear power station and an in-service power station.

The invention belongs to the technical field of nuclear power, and particularly relates to a three-dimensional scene assisted dynamic monitoring generation system based on a digital twinning technology. According to the invention, a set of auxiliary dynamic monitoring system which is developed based on Unity3D and Web technologies and can support rapid formation of a three-dimensional scene is constructed, private deployment is supported, the security of data is ensured, large-scale model rendering, model importing and loading and rapid data point binding under an industrial scene are solved at the same time, and the method is suitable for large-scale model rendering, model importing and loading and rapid data point binding. The problem that a virtual model and a physical model are lack of linkage in the prior art is solved, alarm rule setting is supported, the alarm rule is automatically matched according to real-time data, alarm information is generated, alarm data are displayed at a three-dimensional end, and meanwhile alarm point positions are marked in a three-dimensional model.