6508 results about "Nuclear power plant" patented technology

The invention discloses an intelligent management system for nuclear power plant personnel situation prediction and risk assessment, and relates to the field of intelligent safety management systems, and the system comprises a data collection unit, a multi-dimensional situation awareness unit, a risk prediction and assessment unit, an intelligent decision intervention unit and a visual interaction unit. And multi-source data acquisition, real-time situation construction, dynamic risk prediction and evaluation, intelligent early warning intervention and information visualization are realized. According to the invention, real-time monitoring, dynamic risk prediction and intelligent management of the safety state of the operating personnel can be realized, and the defects of real-time monitoring, dynamic prediction and intelligent management of the operating personnel in a high-risk area in the prior art are overcome, so that the safety management level is improved, the life safety is guaranteed, and the accident occurrence probability is reduced.

The invention discloses a safety monitoring type stop valve for a nuclear power station, and relates to the field of stop valves for nuclear power stations, the safety monitoring type stop valve comprises a stop valve body and a transverse guide groove, the outer end of the stop valve body is in butt joint with a reserved butt joint pipeline, and a nesting butt joint piece is mounted on the inner side of the transverse guide groove in a nesting manner; and the outer side of the nesting butt joint piece is fixedly connected with a first spring, the first spring is in butt joint with the inner wall of the reserved butt joint pipeline, the self-moving structure is provided with a first reserved air bag, and the first reserved air bag is connected to the interior of the reserved butt joint pipeline in an adhesive mode. According to the safety monitoring type stop valve for the nuclear power station, the connection range of a reserved butt joint pipeline is enlarged in a self-adaptive mode, and different pressures generated by a butt joint supply structure at the rear end of equipment are adjusted in a self-adaptive mode according to the liquid discharging process of different flows in different states; the switching-on range is adjusted in a self-adaptive mode according to the flow change of the contact liquid amount, safety monitoring work is carried out in a self-adaptive mode, and the situation that the liquid flow is too large is prevented.

The invention discloses a primary helium fan health state evaluation system and method based on state estimation, and relates to the technical field of nuclear power station equipment state monitoring and health management, and the system comprises a data acquisition unit, a feature extraction unit, a state estimation unit and a health evaluation unit. According to the system, strategies of multi-sensor data fusion, mechanism data hybrid modeling, active incremental learning and the like are adopted, and an end-to-end health state evaluation model is constructed; and the block chain technology is introduced to realize data security sharing and trusted computing. According to the system, multi-source heterogeneous data can be comprehensively utilized, the health state of the main helium fan can be automatically and accurately evaluated in real time, and a reliable basis is provided for intelligent operation and maintenance decision making. The safety and economical efficiency of the nuclear power station are improved, and intelligent development of nuclear power equipment is promoted.

The invention relates to the technical field of pipeline welding seam identification and measurement, aims to solve the problem of uncontrollable data acquisition quality and the problems of robustness and precision of single-feature welding seam extraction, and provides a nuclear power station pipeline welding seam automatic identification and measurement method which comprises the following steps: accurately acquiring pipeline data under a self-adaptive front view posture; carrying out point cloud data processing on the collected data, and carrying out fitting of a pipeline model after segmenting out part of point cloud of the pipeline; after pipeline modeling is completed, a multi-dimensional data fusion method is adopted for weld joint recognition; and after the welding seam area is back projected back to the three-dimensional point cloud space, three-dimensional point cloud of the welding seam area is obtained, modeling is conducted on the welding seam area in combination with the pipeline model, and finally measurement data of the welding seam are obtained. According to the invention, automatic hand-eye calibration and multi-camera calibration of the guiding system can be realized without manual intervention.

The invention relates to a nuclear power enclosed bus intelligent monitoring model based on big data. The model specifically comprises a plurality of technical links such as data acquisition, cleaning preprocessing, feature extraction and selection, modeling and algorithm design, health condition evaluation and monitoring and the like. The intelligent monitoring module designed by the invention realizes comprehensive, real-time and intelligent monitoring of the operation state of the enclosed bus through integrating a plurality of links such as data acquisition, cleaning, feature extraction, modeling prediction and the like; real-time monitoring and early warning functions are realized by combining an Internet of Things technology and a cloud computing platform; a user is helped to quickly know the equipment state and make a scientific and reasonable operation and maintenance decision through display and decision support functions; potential faults are found in time through comprehensive monitoring and intelligent evaluation of the operation state of the enclosed bus, and effective measures are taken for processing, so that the safety and reliability of equipment are enhanced, and long-term stable operation of a nuclear power station is guaranteed; the intelligent monitoring model adopts a modular design and is easy to adapt to different monitoring requirements and scenes.

The invention relates to the technical field of nuclear power plant equipment inspection and data transmission management, and provides a nuclear power plant equipment inspection data transmission management method and system. According to an existing nuclear power plant equipment inspection system, reliable transmission and intelligent processing of data are difficult to achieve in complex high-radiation, high-humidity and strong-electromagnetic-interference environments, the data are prone to interference in the inspection process, and the fault detection precision is insufficient. The device state information is dynamically collected in real time through the multi-modal data collection technology, the sampling frequency is adjusted according to the environment change through the fuzzy logic control algorithm, and the timeliness and accuracy of data are improved. After data preprocessing, high-dimensional fusion and feature extraction of multi-modal data are realized through a Bayesian network and a deep neural network (DNN). The system realizes intelligent inspection and data transmission management of nuclear power plant equipment in a high-interference environment, has high reliability and real-time adaptability, and can be widely applied to an intelligent safety inspection system of a nuclear power plant.

An integrated energy system includes a nuclear thermal plant situated on a nuclear site. The nuclear thermal plant produces thermal energy that is transported to a thermal energy storage system located outside the nuclear site. The thermal storage system is thermally coupled to a power generation system which is also remote to the nuclear site. By this arrangement, the nuclear thermal plant is isolated and decoupled from the power generation system. The nuclear thermal plant may supply thermal energy upwards of 800° C. or more to be stored at the thermal energy storage system until needed such as for industrial heat, power generation, or other uses. The thermal storage system is source agnostic, and one or more additional thermal energy generators, such as additional nuclear reactors, solar thermal plants, or other thermal energy generators can be coupled to a common thermal storage system and power generation system.

The invention discloses a nuclear power plant radiation environment monitoring method and system, and the method comprises the steps: collecting the real-time monitoring data of a nuclear power plant radiation environment, and obtaining an environment monitoring real-time data set; performing dynamic threshold comparison on the environment monitoring real-time data set to generate an abnormal identifier or a normal feature vector; under the condition that the abnormal identifier is not generated, inputting the normal feature vector into a pre-trained environment trend prediction model, and outputting a radiation environment change trend curve and a potential abnormal probability in a future preset time period; and based on the change trend curve and the potential abnormal probability, generating graded early warning information, and finally outputting a monitoring early warning result including an early warning grade, prediction time efficiency and a coping strategy. According to the embodiment of the invention, the method can achieve the intelligent monitoring of the whole process of the radiation environment from the abnormal recognition to the prediction intervention, and improves the early warning accuracy, timeliness and decision support capability.

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 nuclear power robot maintenance, and discloses an intelligent inspection and fault diagnosis system for a nuclear power robot, which integrates a high-precision sensor network, captures operation environment data of nuclear power facilities in real time, and constructs a rich training data set in combination with operation and maintenance records and historical fault data. Through a machine learning algorithm, a nuclear power facility inspection model and a fault diagnosis model are systematically trained, and automatic identification of abnormal conditions, preliminary classification of fault types and deep analysis of specific reasons and positions of faults are realized. Meanwhile, the system innovatively constructs an error correction model, and further optimizes the accuracy of inspection and fault diagnosis. And the data analysis unit automatically generates a detailed inspection report and a fault diagnosis report by using the trained model, thereby providing powerful technical support for safe and stable operation of the nuclear power station.

The invention provides an integrated containment pressure suppression, filtration and discharge system. The integrated containment pressure suppression, filtration and discharge system comprises a containment, a discharge valve, a discharge pipeline, a spray pipe, a first-stage pressure suppression water tank, a second-stage pressure suppression water tank, a baffle plate steam-water separator, an expansion tank, a rupture disk structure, a combined metal fiber filter layer, a radioactivity monitor, a first stop valve and a second stop valve. The two-stage pressure suppression water tank is arranged, the high removal efficiency of airborne radioactive substances is achieved through two-stage bubbling water washing, then the combined metal fiber filter is arranged by means of an existing cabin, and the requirements for rapid pressure reduction and radioactive substance removal of the containment under the LOCA accident working condition can be met; meanwhile, the problem that the containment filtering and discharging system of the existing nuclear power station occupies too many resources is solved, and the economical efficiency is high.

The invention provides a device and method for removing aerosol based on a charged spraying coupling pool washing mechanism, and belongs to the field of nuclear auxiliary systems. The problem that radioactive aerosol particles generated when a radioactive contamination structure in a reactor is cut underwater can be released into the external environment is solved. Wherein the underwater laser cutting assembly is used for cutting a to-be-cut piece; the auxiliary gas chamber is communicated with the laser cutting nozzle; the aerosol charging assembly can enable aerosol particles generated by underwater laser cutting to carry negative charges; the baffle can gather the aerosol particles and guide the aerosol particles to the aerosol charging assembly; the liquid drop charged spraying assembly can spray liquid drops carrying positive charges, the liquid drops carrying positive charges and aerosol particles carrying negative charges can attract each other and fall to the liquid level, and the Venturi washing assembly can extract gas above the liquid level and spray the gas below the liquid level. The device can efficiently remove radioactive aerosol particles generated by cutting and disassembling radioactive contaminated components in a nuclear power plant, and radioactive contamination to the environment is prevented.

The invention particularly relates to a method for predicting the service life of a boric acid solution corrosion concrete member in a nuclear power plant. The method comprises the following steps: determining boric acid solution accelerated corrosion concrete member test control parameters; based on the boric acid solution accelerated corrosion concrete member test control parameters, boric acid solution accelerated corrosion concrete member tests are carried out in groups; constructing a boric acid solution corrosion concrete member life prediction model based on boric acid solution accelerated corrosion concrete member test data; and predicting the boric acid solution corrosion concrete member service life based on the boric acid solution corrosion concrete member service life prediction model. According to the method, a model for predicting the service life of the concrete member corroded by the boric acid solution is established by considering the water-binder ratio of the concrete, the temperature, the concentration of the boric acid solution and the corrosion time on the basis of research test results of physical properties and macroscopic mechanical properties of the concrete member corroded by the boric acid solution or field actual measurement data; and the service life of the boric acid solution corroded concrete member is predicted.

The invention provides a nuclear power safety valve remote monitoring and fault diagnosis method and system, and the method comprises the steps: obtaining multi-modal data collected through a sensor array; performing preprocessing and feature extraction on the multi-modal data to obtain various features of the multi-modal data; the fault type of the nuclear power safety valve is predicted based on the multiple features in combination with a CNN-LSTM hybrid model, and a preliminary fault type prediction result is obtained; and performing fuzzy logic optimization on the preliminary fault type prediction result to obtain a final fault type prediction result, and performing real-time alarm according to the final fault type prediction result. Relevant parameters of the parameterized three-dimensional digital twinborn model of the nuclear power safety valve are obtained in real time, and data of the parameterized three-dimensional digital twinborn model of the nuclear power safety valve are updated through the relevant parameters; through the parameterized three-dimensional digital twinborn model of the nuclear power safety valve, the operation and maintenance information of the fault part corresponding to the final fault type prediction result is visualized, and the accuracy, comprehensiveness and operation and maintenance assistance of fault prediction are improved.

The invention discloses a dynamic monitoring-based deaerator water supply control method and system for a nuclear power plant, and relates to the field of deaerator water supply control, and the method comprises the steps: firstly, through a hybrid online identification algorithm, analyzing a historical valve position instruction and a water supply flow sequence in real time, and dynamically estimating the local gain and hysteresis width of a valve under the current working condition; then, the parameters identified in real time are utilized to carry out prospective compensation on the expected flow variation calculated by the main controller. In other words, the instruction amplitude is adjusted according to the estimated local gain, and it is ensured that consistent flow response can be obtained under different loads; meanwhile, when the instruction is reverse, the compensation amount is actively applied according to the estimated hysteresis width so as to eliminate the adjustment dead zone and oscillation caused by hysteresis. In this way, the nonlinear object of the valve is equivalent to a linear link with consistent response, and the stability and accuracy of the deaerator water level control system in the full working condition range are remarkably improved.

The invention discloses a nuclear power plant multi-sensor failure detection and signal reconstruction method, and relates to the technical field of sensor measurement and signal reconstruction. After preprocessing the measurement data, constructing a training set; extracting a part of training set data, simulating a sensor fault by using the sensor fault mechanism model to obtain simulated sensor fault data, and constructing a test set; detecting the working state of the nuclear power plant sensor based on the training set and test set data, positioning the specific position of the fault sensor, and outputting the normal data of the sensor or the position data of the fault sensor; using a local fusion mode to reconstruct failure data of the fault sensor, and outputting reconstructed sensor data; the method can accurately judge the working state of the nuclear power plant sensor.

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 invention relates to the technical field of nuclear power robots, discloses a nuclear power robot accurate positioning and path planning method, and aims to construct a three-dimensional environment model for a complex and changeable environment in a nuclear power station, and express the environment as a grid map containing environment characteristic information. According to the method, a comprehensive state space is defined, the three-dimensional position, obstacle distribution, radiation intensity and energy state of the nuclear power robot are covered, and real-time updating of dynamic obstacles is considered. The action space defines all possible moving actions of the robot so as to ensure the planning flexibility. By defining a comprehensive cost function, the length of a path, radiation exposure, energy consumption and collision risk are evaluated, and a strategy is formulated with the purpose of minimizing accumulated cost. According to the method, the heuristic search algorithm is combined with the reinforcement learning strategy to carry out path planning, so that the planning precision and adaptability are improved.

The invention provides a nuclear power station flow channel joint dredging robot applying an image recognition algorithm. The robot comprises an image recognition sensing system, a robot moving navigation system, a dredging operation system and a safety monitoring system. The image recognition sensing system is used for collecting an image in the flow channel through a high-resolution camera and analyzing and recognizing sludge and sundries in the flow channel according to the image; the robot mobile navigation system is used for realizing positioning, path planning and autonomous movement of the robot; the desilting operation system is used for removing and collecting sludge and sundries in the flow channel; the safety monitoring system is used for monitoring the running state and the working environment of the robot in real time and ensuring the safety and the reliability of the dredging process of the robot; by integrating image recognition, automatic navigation and a safety monitoring system, efficient, accurate and safe flow channel dredging operation is achieved.

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 provides a reactor building, an arrangement method thereof and a nuclear power station. The arrangement method of the reactor building comprises the following steps: dividing a vertical surface space of the reactor building into layers along the vertical direction, arranging a reactor pit and a containment pit on a third underground layer, and arranging a first loop main equipment compartment, a second loop main equipment compartment and a third loop main equipment compartment on a second underground layer and above the second underground layer. A high-position refueling water tank of the passive safety injection system is arranged in a high-position refueling water tank compartment of a first underground layer, so that water in the high-position refueling water tank can submerge a reactor pit and main equipment of a reactor coolant system under the action of gravity. The method comprises the following steps: arranging core equipment of a passive special safety system in a containment; a special safety system related to safety can resist external disasters by means of the containment, and meanwhile, the system does not need to be switched between the inside and the outside of the containment during operation, so that the reliability of the system is greatly improved.

The invention particularly relates to a discharge machining simulation control system for a nuclear power plant in a high-radiation boron-containing water environment, which belongs to the technical field of special maintenance in the high-radiation environment of the nuclear power plant and comprises a man-machine interaction system, a discharge machining control system and subsystems. Each subsystem comprises a pulse power supply system, a servo power system, a washing system, a purification system, a grounding system and a tool system; the man-machine interaction system is used for man-machine interaction and displaying the discharge machining implementation data fed back by the subsystems; the electric discharge machining control system is used for generating an electric discharge machining instruction according to the man-machine interaction information and controlling the subsystems to cooperate to perform electric discharge machining work; and each subsystem is used for implementing electric discharge machining work according to the electric discharge machining instruction and feeding back electric discharge machining implementation data. According to the invention, simulation control of discharge processing in the high-radiation boron-containing water environment of the nuclear power plant is realized.

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 relates to the technical field of nuclear power modeling, in particular to a nuclear power plant control model construction method, electronic equipment and a storage medium. According to the nuclear power plant control model construction method, a control logic diagram and modeling demand information of a target nuclear power plant control system need to be acquired firstly; performing simulation demand analysis on the control logic diagram based on the modeling demand information to determine a simulation implementation constraint; performing function block icon analysis on the control logic diagram, determining a plurality of target modeling elements, performing function block identifier analysis on the control logic diagram, determining a simulation constant value parameter and a parameter transmission relation, and generating a transmission point-to-point file; constraining the plurality of target modeling elements based on simulation implementation, and generating a simulation control chart; and carrying out model loading on the basis of the simulation control chart, the simulation fixed value parameters, the transmission pair point file and the parameter transmission relation, and generating a nuclear power plant control model. Therefore, the quality and efficiency of the nuclear power plant engineering simulation machine in the modeling link of the nuclear power plant control model can be improved.

The invention discloses a nuclear power plant fault diagnosis method and device, and the method comprises the steps: collecting nuclear power plant data, training and constructing an edge end model group and a cloud model group according to the nuclear power plant data, and the nuclear power plant data comprises operation regulations, real-time operation data and historical operation data; deploying the edge end model group to an edge computing node near equipment in a plant, and deploying the cloud end model group to a cloud platform; inputting the real-time operation data of the nuclear power plant into the edge end model group, detecting a fault type, reconstructing sensor parameters if the fault type is sensor abnormality, and uploading an abnormality report to the cloud platform if the fault type is system abnormality, and reasoning and tracing the abnormal report through the cloud model group, and pushing fault information and a decision scheme.

The invention discloses a steam generator water level control method, system and device based on digital twinning, and the method comprises the steps: obtaining the detection information obtained through the detection of a sensor in real time, and outputting the actual measurement water level to a water level regulator, so as to obtain the feed water flow regulation amount; the detection information is analyzed according to the real-time online heat balance model to obtain an analysis result, the analysis result and the feed water flow adjusting amount are output to a first flow regulator, and the first flow regulator correspondingly outputs a control instruction to a feed water adjusting valve for feed water flow adjustment. According to the control method, by means of the digital twinning technology and the numerical simulation technology, the water level control process is improved to achieve accurate adjustment, and the operation reliability, the equipment safety, the operation convenience and the operation efficiency of the nuclear power station steam generator are improved.

The invention provides monitoring equipment and system for monitoring a reactor core of a nuclear power plant. The monitoring device comprises a data preprocessing module, a model updating module, a monitoring module, a shared data pool and a monitoring interface module. On one hand, on-line monitoring of a reactor core is realized by tracking actual operation data of a reactor, and the accuracy of a monitoring result is improved; and on the other hand, the reactor core three-dimensional power distribution reconstruction is carried out in combination with the actual measurement current, so that the monitoring result (such as the second reactor core physical parameter) obtained based on the reconstructed reactor core three-dimensional power distribution is more matched with the actual operation condition of the reactor core, and the accuracy is higher.