79 results about "Nuclear safety and security" patented technology

The invention discloses a nuclear safety simulation verification method and device based on digital twinning and a medium, and relates to the technical field of nuclear engineering and digital twinning, and the method comprises the steps: training a physical information neural network based on a digital twinning initial model in combination with a nuclide transport equation and a thermal hydraulic equation, and outputting a nuclear safety multi-field simulation result; based on a nuclear safety multi-field simulation result, establishing a space-time diagram structure, extracting dynamic evolution characteristics by using a space-time diagram convolutional network, and outputting a nuclear accident propagation path and a risk distribution diagram; according to the method, the space-time diagram structure is constructed, the space-time diagram convolutional network is utilized to extract the dynamic evolution characteristics, the nuclear accident propagation process is modeled as cascade response in the space-time domain, and the reliability of the nuclear accident propagation process is improved. And the accuracy, the foresight and the intelligent level of nuclear security simulation verification are improved.

The invention provides a shell-and-tube phase change heat storage system for a nuclear reactor containment and a nuclear accident heat energy management method, and belongs to the technical field of nuclear safety engineering and heat energy storage. The problems that an existing shell-and-tube heat reservoir is designed for industrial waste heat recovery and is not suitable for nuclear accidents, and the internal space structure of a containment is complex and limited are solved. The heat storage units are distributed in parallel, and each heat storage unit comprises a shell and a plurality of heat exchange tube bundles arranged in the shell; the heat storage unit has an interchangeable heat storage medium arrangement mode which comprises the first mode that the space in the heat exchange tube bundle is filled with a phase change material, and accident steam flows through a shell side channel between the shell and the heat exchange tube bundle; in the second mode, the shell side space between the shell and the heat exchange tube bundle is filled with the phase change material, and accident steam flows through an in-tube channel of the heat exchange tube bundle; and the accident steam passively flows through the channel which is not filled with the phase change material under the driving of the pressure difference. The method is used in the phase-change heat storage field.

The invention relates to the field of post-accident gamma dose rate measurement, and provides a post-accident gamma dose rate dynamic measurement method and system based on multi-detector fusion, and the method comprises the steps: obtaining original signal data and environment parameter data; processing the original signal data, the environmental parameter data, the accumulated radiation dose and the displacement damage energy by adopting a deep learning network to obtain corrected signal data; processing the correction signal data and the environmental parameter data through a time sequence prediction network to obtain a dynamic weight distribution result of each detector; processing the correction signal data and the dynamic weight distribution result based on a self-calibration confidence evaluation network to obtain a confidence evaluation result; and processing the correction signal data, the dynamic weight distribution result and the confidence evaluation result through a weighted fusion algorithm to obtain a dynamic measurement result of the gamma dose rate after the accident. According to the invention, high-precision dynamic measurement, real-time damage compensation and nuclear safety level reliability evaluation of the gamma dose rate after an accident are realized.

The invention discloses a parameter optimization method and system based on an agent model and multi-algorithm gradient collaboration, and relates to the technical field of nuclear engineering and nuclear security, and the method comprises the steps: firstly determining a nuclear facility parameter combination, carrying out the high-fidelity calculation through a Monte Carlo program to obtain a Keff value, and constructing a training set; training a micro-proxy model capable of predicting a Keff value and gradient information through a feedforward neural network in combination with a back propagation algorithm, taking the micro-proxy model as a target function, taking the minimum absolute error of a Keff predicted value and a target value as an optimization target, and generating candidate parameter solutions through global exploration of a hybrid optimization algorithm; and an optimal parameter combination candidate solution is obtained through gradient-assisted local optimization, and finally, through Monte Carlo program verification, if the error reaches the standard, the optimal parameter combination candidate solution is used as a final parameter combination solution. The problem that a parameter optimization method in the prior art cannot give consideration to calculation efficiency and precision is solved.

The invention discloses a multi-stage cascade semantic analysis framework of a nuclear security level control code generation tool, which comprises an input layer, an analysis module layer, an error processing layer and an output layer, and is characterized in that the input layer is used for receiving and preprocessing a control model xml file, verifying a file format and preliminarily checking grammar; the analysis module layer is used for analyzing post grammar, namespace, type, clock, causal relationship and initialized semantic analysis tasks of the file after receiving the analysis request to obtain analysis results; the error processing layer is used for collecting, classifying, positioning and report generating various error information appearing in the analysis module layer; and the output layer is used for generating and outputting a standardized analysis report and an optimization suggestion. And a pipelined cascade structure is adopted, so that efficient semantic analysis is realized. Through an innovative error processing mechanism and an optimization strategy, the analysis efficiency and accuracy are remarkably improved, and a reliable guarantee is provided for software development of a digital instrument control system of the nuclear power station.

The invention relates to a nuclear power system equipment nuclear safety performance evaluation method, which comprises the following steps of: obtaining a complete system list of a power plant, and screening the system list according to a nuclear safety function correlation condition to obtain a function list meeting a nuclear safety function requirement; classifying the function list based on the operation state to obtain a category system classification of the nuclear safety related system equipment meeting the operation state classification standard; performing performance index making according to the category classification to obtain a performance index making result of the nuclear safety related system equipment; and performing nuclear safety performance evaluation on the nuclear safety related equipment in the preset time period according to the performance index formulating result to obtain a nuclear safety performance evaluation result in the preset time. Through systematic equipment screening and classification, scientific and reasonable performance index formulating and dynamic performance evaluation based on actual operation data, the nuclear safety performance of the nuclear safety related equipment in the preset time period is evaluated; and refined evaluation of nuclear power plant system equipment nuclear safety performance is realized.

This invention relates to the field of nuclear safety equipment testing technology. It provides a method for optimizing parameters in accelerated reliability testing of nuclear safety-grade valves. The method involves the following steps: establishing a correlation model between accelerated stress and life parameters; calculating the acceleration factor and formulating an initial test plan; deriving the theoretical sample size based on the success-failure test method combined with confidence requirements; constructing an extended coefficient table using the range-extended test method to optimize test parameters; generating multiple accelerated test plans through chi-square distribution verification; eliminating plans that do not meet the life characteristic threshold; determining the optimal sample size, number of failures, and test cycle through comprehensive test cost and risk analysis; and finally outputting a complete test plan including the action interval time. This method solves the problems of limited test samples, insufficient failure data, low confidence levels, and difficulty in adapting accelerated models in existing high-reliability valve technologies.

The invention discloses a hot standby redundancy switching method and system based on credible state strategy judgment and a medium. The method comprises the following steps: acquiring DCS input data; data verification is carried out on DCS input data based on a redundant communication network between the master controller and the slave controller; based on a trusted state strategy synchronization mechanism, performing service data synchronization on the verified DCS input data between the master controller and the slave controller; the service data synchronization comprises master-slave controller credible state strategy data synchronization and master-slave controller service data synchronization; when the master controller diagnoses a self-diagnosis fault or a communication fault, whether the master controller and the slave controller need to be switched or not is judged by combining the state of the slave controller; if switching is needed, according to the fault state, master-slave arbitration is carried out based on a preset switching condition truth table, and switching of master-slave controller state identification is completed. According to the invention, full-station communication fault detection and master-slave switching of the domestic nuclear safety level DCS field control station are realized, and the safety of the domestic nuclear safety level DCS is improved.

The application discloses a kind of digital fuel physics supervision method and system suitable for heavy water reactor, it is related to nuclear reactor fuel management technical field, system includes data acquisition module, document scale calculation interface, system management module and central processing module, central processing module configuration basic data, new fuel, FCO, spent fuel, dry storage area management unit.Method is standardized by data acquisition, whole-process digital control, dynamic monitoring and tracing three steps, realize fuel full life cycle closed-loop management.System adopts PDA to cooperate bar code / RFID to realize entity information acquisition and offline synchronization, constructs hierarchical correlation model, with new fuel isolation control, FCO closed-loop approval, spent fuel transfer verification, fine authority control and other functions, can improve management efficiency, reduce human error, strengthen data tracing and operation standardization, guarantee nuclear safety, provide support for management decision, suitable for heavy water reactor fuel physics supervision and whole-process management.

The invention belongs to the technical field of nuclear power station operation management and nuclear safety, and relates to an automatic scheduling method and system for nuclear emergency duty, and the method comprises the steps: obtaining multi-source data related to nuclear emergency duty, and carrying out the fusion coding of heterogeneous features in the multi-source data through employing a multi-head attention mechanism; on the basis of the encoded features, a deep reinforcement learning model is adopted, and an initial scheduling scheme is generated under the condition that multiple types of constraints are met; the deep reinforcement learning model is realized based on a DQN network; and performing conflict optimization and multi-dimensional automatic verification on the initial scheduling scheme based on a tree search algorithm, and outputting a final scheduling scheme. By adopting the method, the dynamic response and fairness are obviously improved; the scheduling efficiency and the compliance are greatly improved; and the system elasticity and stability are obviously enhanced.

The invention discloses a nuclear power station dragon scale platform safety level DCS configuration maintenance downloading method, system and device and a medium. The method comprises the steps of obtaining system parameters of a safety level distributed control system; according to the system parameters, the security-level distributed control system is divided into a shutdown protection group and a special sequence; the shutdown protection group sequentially performs configuration maintenance downloading work of the distributed control system within a set time threshold range, and after the downloading work is completed, a time system is recovered and a state is verified; and specifically setting a sequence to check the state of the equipment, disconnecting the control electric isolation, then carrying out the configuration maintenance downloading work of the distributed control system, and after the downloading work is completed, recovering power supply and verifying the state. According to the invention, the risk of the security-level distributed control system can be controlled in a decentralized manner, the overall downloading risk level is reduced, the equipment misoperation probability is effectively avoided, and the problems of uncontrollable risk, abnormal equipment linkage and low operation efficiency in the traditional offline updating of the nuclear security-level digital control system are solved.

The invention relates to a nuclear security supervision data migration method and device, computer equipment, a storage medium and a computer program product. The method comprises the steps of determining a to-be-migrated field corresponding to a to-be-migrated data form in response to a data migration instruction for the to-be-migrated data form corresponding to the nuclear security supervision system; determining a first data classification result of the to-be-migrated field and a second data classification result of the field value of the to-be-migrated field; determining a target data classification result of the to-be-migrated field according to the first data classification result and the second data classification result; determining a migration classification template corresponding to the to-be-migrated field according to the target data classification result; the migration classification template is used for representing a mapping relation of the to-be-migrated field between the nuclear security supervision system and a target nuclear security supervision system; and according to the migration classification template, migrating the to-be-migrated field from the nuclear security supervision system to the target nuclear security supervision system. By adopting the method, the data migration efficiency can be improved.

A system for containing a nuclear reactor is disclosed. The system includes a nuclear containment structure comprising a plurality of metallic rings stacked axially to form the nuclear containment structure. The nuclear containment structure includes a central chamber that comprises a volume enclosed by the inner wall of each of the plurality of metallic rings, and also includes a plurality of auxiliary chambers. The central chamber encloses a nuclear reactor vessel, wherein the inner wall of the plurality of metallic rings is flush with the nuclear reactor vessel. Cooling channels also exist within the nuclear containment structure. The nuclear containment structure is configured to shield the nuclear reactor vessel from kinetic events originating external from the nuclear containment structure and to shield an external environment from kinetic events within the nuclear reactor vessel.

The invention discloses a function distribution method and system of a nuclear safety level digital instrument control system and a medium. Relates to the technical field of nuclear safety level instrument control design. The method is improved on the basis of the traditional technology, an FD / SAMA graph is analyzed to construct a same-level system interface graph and an internal system relation graph on the basis of meeting function dispersion and diversity design, and the internal system interface graph and the internal system relation graph are constructed on the basis of a same-class merging rule, a priority rule and a mutual exclusion rule. Performing function distribution on each site of the nuclear security level digital instrument control system by combining a same-level system interface diagram and an internal system relation diagram, performing system operation calculation on each group of function distribution schemes, and screening out an optimal function distribution scheme; the function distribution design is optimized, the coupling between systems is reduced, the response time, the load rate and the margin of each subsystem are ensured to meet the requirements, the design quality is improved, the design efficiency is improved, the later design iteration is reduced, and the design period is shortened.

The application discloses an experimental test and evaluation method for simulating breakage of a nuclear fuel rod and escape characteristics of fission products, which comprises consideration of similarity criteria, and ensures that the cylindrical geometry of the broken fuel rod can simulate the flow characteristics of the flow field near the break along the axial direction of the cylindrical surface; and the flow similarity in the experimental section is realized by Re>10 5 The flow field enters the self-modification area; the critical break diameter is determined based on the blocking flow theory; the specific experimental conditions are determined by single variable control processing of multiple factors; the release rate of fission products per unit time and the escape rate of fission products finally entering the coolant are divided into two experiments of fuel rod constant internal pressure and fuel rod sealing for measurement; and high-confidence uncertainty evaluation is carried out by using A and B two types of evaluation components; and the experimental results are used to fit the fission product escape rate coefficient model. The application solves the problems of poor reliability of experimental extrapolation, blind selection of working conditions and incomplete evaluation system, and provides high-precision benchmark data for nuclear safety analysis programs.

The application discloses a nuclear safety level display control device based on optical fiber networking, and relates to the field of digital control systems of nuclear power plants. The nuclear safety level display control device serves as a node of multiple independent optical fiber networks. Each optical fiber network comprises multiple safety level control stations and multiple nuclear safety level display control devices. The nuclear safety level display control device comprises a control module, a data processing module, a fault diagnosis module, a display touch module and multiple optical fiber communication modules. The control module is connected with the display touch module. The data processing module is connected with the control module and each optical fiber communication module. Each optical fiber communication module is connected with the data processing module and the optical fiber of one optical fiber network. The fault diagnosis module is connected with the control module, the data processing module and each optical fiber communication module. The nuclear safety level display control device transmits data through high-speed optical fiber networking technology, meets the safety level requirement, improves the data transmission rate, and avoids data delay reception and loss.

A structure and process for containing a nuclear reaction is disclosed. The structure and process may involve a nuclear containment structure including a plurality of metallic rings stacked axially to form the nuclear containment structure, the nuclear containment structure being configured to: mitigate, by using a physical barrier, the movement of radionuclides from inside a containment structure to a surrounding space; shield, by varying the alloy properties throughout the containment structure, an exterior of the containment structure from radiation produced inside of the containment structure; regulate, by transferring thermal energy, a temperature within the containment structure; regulate, by storing thermal energy, the temperature within the containment structure; shield, components within the nuclear containment structure from kinetic events external to the nuclear containment structure; and shield, the external environment, from kinetic events within the nuclear containment structure.

The application belongs to the technical field of sealing and particularly relates to a D-shaped sealing ring reinforcing structure for a seawater butterfly valve and a manufacturing process. The sealing ring reinforcing structure comprises a sealing ring body, and a through hole is formed in the sealing ring body. The sealing ring body is annular. Uniformly distributed through holes are formed in the sealing ring body. The sealing ring body comprises a framework fabric and rubber, and the framework fabric has two layers and is nested in the rubber. The application has the beneficial effects that the application has a simple structure, is simple to process and manufacture, has good adhesion between the framework fabric and the rubber, and has no large tearing and damage after installation and use, and the product quality is obviously better than that of the original sealing ring. The application can meet the high reliability use requirements of nuclear power plants and has a positive effect on improving nuclear safety.

The invention provides an automatic execution method and device for digital regulations of a nuclear power plant, equipment and a medium. The method comprises the following steps: acquiring operation data of nuclear power plant equipment from a distributed control system in real time; determining a to-be-executed digital operation instruction according to the operation data; automatically scheduling and executing a plurality of modular operation units corresponding to the digital operation specification; for the currently executed modular operation unit, sending an operation instruction to the distributed control system, and receiving a feedback signal of the distributed control system in response to the operation instruction; according to the feedback signal, whether the current modular operation unit is executed successfully or not is judged, and if yes, the next modular operation unit is automatically triggered to be executed until the digital operation instruction is executed completely. Through modularization and automatic execution, human errors are remarkably reduced, and the nuclear safety level is improved; the regulation execution time is greatly compressed, and the emergency response capability is enhanced; and intelligent closed-loop management is realized by means of fault diagnosis and full-process logs.

The invention belongs to the technical field of nuclear security supervision, and particularly relates to an automatic extraction and entry method for nuclear security supervision document data. Comprising the following steps: step 1, sorting a nuclear security supervision document template and key fields; 2, constructing a nuclear security supervision document intelligent extraction model; and step 3, automatically inputting data and configuring items. The method for automatically extracting and inputting the nuclear security supervision document data has the beneficial effects that text recognition can be carried out on the nuclear security supervision documents of various formats and templates, key information fields are automatically extracted from the documents according to requirements and are filled into a fixed form, and the efficiency is improved. And automatic extraction and entry of nuclear safety supervision data are realized. By developing a corresponding intelligent system, the automatic extraction and entry accuracy of the nuclear safety supervision data can reach 90% or above, the actual application requirements are met, the labor cost can be remarkably reduced, and the obtaining efficiency and accuracy of the nuclear safety supervision data are improved.

The application relates to the technical field of instrument control simulation, in particular to a simulation device and method of a nuclear safety level DCS (Distributed Control System) field control station and a storage medium, the device comprises a plurality of virtual field control stations used for simulating the existing field control station, the virtual field control station comprises a data processing module, a simulation processing module, a virtual board card module and a communication module; the method comprises the following steps: carrying out inter-station communication connection and external station communication connection of the virtual field control station; carrying out data processing of the virtual field control station; creating a virtual board card; processing simulation instructions to complete simulation of the virtual field control station on the existing field control station; various types of board cards are virtually created through the virtual board card module, different types of board cards are individually virtually created, communication in the station and external station communication are realized through the communication module, shared memory is created through the data processing module, data exchange between modules is more efficient, and finally simulation processing is realized through the simulation processing module.

A nuclear purification cabin is arranged in the breeding work ship, a coil pipe is arranged in the nuclear purification cabin from top to bottom, a precipitant solution is connected into the coil pipe, seawater is sent into a nuclear radiation primary detection device by a seawater pump to be detected, after nuclear radiation primary detection is qualified, the seawater enters a breeding cabin through a pipeline, and otherwise, the seawater enters the breeding cabin through a pipeline. The seawater enters the coil pipe again, enters the standing cabin through the coil pipe and waits for secondary detection of nuclear radiation, qualified seawater is fed into the culture cabin after the secondary detection is qualified, and otherwise, the seawater is circulated back to the coil pipe and enters the standing cabin again after being filtered by the coil pipe. According to the invention, nuclear radiation detection is carried out on the seawater entering the culture work ship, and the seawater with the nuclear radiation not exceeding the standard is injected into the culture cabin. In the nuclear purification operation process, no new pollution is generated to seawater, and the nuclear safety of the seawater in the culture cabin is ensured. And sediments formed by radionuclides are independently and specially stored, and are treated after the breeding work ship arrives at the shore, so that extra nuclear pollution is not caused.

The invention discloses a neutron source based on an FRC linear magnetic confinement nuclear fusion device, and relates to the technical field of fusion devices. The neutron source comprises a vacuum chamber for providing a vacuum environment for fusion reaction; the magnet system is arranged outside the vacuum chamber and is used for ionizing gas in the vacuum chamber and generating fusion reaction; the neutron extraction system is arranged in the fusion reaction generation area of the vacuum chamber and is used for extracting epithermal neutrons; the neutron lead-out system comprises a neutron lead-out channel, a shielding and reflecting device and a filter, the shielding and reflecting device is arranged outside the lead-out channel and used for shielding and reflecting neutrons, and the filter is arranged in the neutron lead-out channel and used for filtering fast neutrons, thermal neutrons and photons; the neutron source provided by the invention has the advantages of higher neutron yield, simple and compact structure, effectively reduced overall device volume, low construction and maintenance cost and small nuclear safety prevention and control pressure, and can be used in various fields of medical treatment, scientific research, military industry and the like.

The application discloses a correction testing device and method for containment penetration sealing detection and evaluation, and belongs to the field of nuclear safety. The device comprises a main simulation module (radiation-resistant acrylic cylinder), a pore simulation module (a plurality of diameter thin wires form a preformed through hole), a pressurized sealing module, a sound insulation anti-interference module and a measurement adaptation module. By establishing a'sound intensity-leakage rate' calibration curve in the laboratory and combining with the field environment background correction, the quantitative evaluation of the leakage rate of BC type penetration under low pressure conditions based on the ultrasonic leak detection method is realized. The method flow is as follows: device sealing verification, flow supplement method for determining standard leakage rate, ultrasonic measurement for recording test sound intensity and background, calculating net sound intensity, establishing a calibration model by cubic polynomial fitting, measuring the field measurement environment background and calculating the linear amplitude correction coefficient, and substituting the calibration model to obtain the field leakage rate. The device takes into account the influence of field noise, is convenient for online rapid detection of nuclear island, reduces detection cost and radiation exposure risk of personnel.

The invention discloses a nuclear power risk analysis method combining internal event probabilistic safety analysis and power generation risk assessment, and the method comprises the steps: S1, determining an internal originating event of a nuclear power plant, and determining an analysis boundary range; s2, analyzing the originating event sequence, and determining a response process and a corresponding success criterion; s3, constructing a power generation risk event tree model; s4, aiming at the event sequence in the S3, constructing a kernel security risk event tree model through a probabilistic security analysis method; and S5, selecting the system fault tree model in the model in the step S4 to carry out FMEA (Failure Mode and Effect Analysis), FMEA (Failure Mode and Effect Analysis), FMEA (Function Event Fault Tree Analysis), FMEA (Function Event Fault Tree Analysis), FMEA (Function Event Fault Tree Analysis) and correlation analysis. According to the technical scheme, the problem that analysis results of a single PSA or GRA nuclear power plant are insufficient is solved, comprehensive analysis of probability safety analysis and power generation risk analysis of the nuclear power plant is achieved while the workload is reduced and the analysis efficiency is improved by combining the two analysis methods, decision support is provided for design, operation and management of the nuclear power plant, and safety and economical efficiency are improved.

The invention relates to the technical field of nuclear security level DCS (Distributed Control System), and discloses a method and a device for online upgrading a functional module of a nuclear security level DCS system. The engineer station completes downloading of the downloading file based on the private network, the main control module receives and verifies the integrity and correctness of the downloading file and then distributes the downloading file to the function module, and the function module receives and verifies the integrity and correctness of the downloading file and then automatically executes updating. Therefore, the remote online upgrading operation of the functional module of the nuclear security level DCS system is realized, and the maintenance efficiency of the nuclear security level DCS system is improved.

The application discloses a kind of based on digital twinning nuclear safety simulation verification method, equipment and medium, it is related to nuclear engineering and digital twinning technical field, including, based on digital twinning initial model, combine nuclide transport equation and thermal hydraulic equation training physical information neural network, output nuclear safety multi-field simulation result;Based on nuclear safety multi-field simulation result, establish space-time graph structure and utilize space-time graph convolution network to extract dynamic evolution characteristics, output nuclear accident propagation path and risk distribution map;To virtual-real alignment nuclear safety digital twinning model executes credibility evaluation, generates nuclear safety simulation verification result, the application constructs space-time graph structure and utilizes space-time graph convolution network to extract dynamic evolution characteristics, nuclear accident propagation process is modeled as the cascading response on space-time domain, improves the accuracy, foresight and intelligent level of nuclear safety simulation verification.

The invention discloses a nuclear security level DCS cabinet check table generation system and method based on a loop table, and the system comprises a drawing reading module which is used for reading different types of electrical design drawings; the template and definition module is used for forming various loop table templates and managing the loop table templates and macro and device attribute information bases; the data analysis module is used for analyzing the electrical design drawing, forming an equipment connection relation chain table and storing the equipment connection relation chain table into a preliminary database; the loop processing module is used for carrying out loop table selection according to the equipment connection relation linked list; performing loop table modeling according to the selected loop table to form a loop database; the check table generation module is used for reading the electrical information in the loop database and automatically generating a check table; reading an index table in the loop database, and finding out a corresponding loop table according to the table name of the loop table; and in combination with a case template, a test case table is formed through conversion. The automation degree of the design process can be effectively improved.

The application discloses a kind of nuclear safety grade DCS system engineering application software logic comparison method and device, it is related to nuclear power technical field, the underlying data in engineering application software is based on in the present application, the logic comparison of different units or different versions of engineering application software is realized, a large number of false positives caused by comparison based on image recognition technology is solved, the misidentification problem caused by the large displacement of the element position in drawing is eliminated, and it is also unnecessary to train through artificial intelligence big model, the workload of designer is reduced, the misidentification of comparison result caused by different algorithm modules used by different designers and different design styles is eliminated, work efficiency and work quality are greatly improved, and logic error caused by human error is avoided.

The invention belongs to the technical field of nuclear power operation safety control, and particularly relates to a nuclear power operation event decision-making system and method based on multi-dimensional rule collaboration. Comprising a data acquisition module, a patrol analysis module, a state positioning module, an exception handling module and an auxiliary decision making module, nuclear power operation data are analyzed and monitored in combination with a time sequence prediction model and a link tracking algorithm, advanced prediction and intelligent processing of abnormal conditions are achieved, accurate and reliable support is provided for nuclear power operation decision making, and the reliability of nuclear power operation decision making is improved. Therefore, the operation safety and reliability of the nuclear power station are improved. The method has the advantages that by combining the link tracking algorithm model and the abnormal event matching strategy, the early-stage and timely early warning and processing of the abnormity are realized, and the probability of nuclear safety accidents is effectively reduced. Based on the process chain monitoring constructed by the nuclear power operation process, the operation state and relevance of each system and equipment of the nuclear power station are grasped in time, potential risks are found in time, and the reliability and the stability of the operation of the nuclear power station are improved.