1402 results about "Nuclear 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 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 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 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 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.

The invention provides an off-site full-range radiation risk evaluation method and system under a severe accident of a nuclear power plant, and the method comprises the steps: S1, building a radioactive accident risk evaluation basic model architecture, adapting to a model demand, and building a corresponding basic database; s2, constructing radioactive smoke plume characteristics after the accident; s3, calculating accident site space gridding and smoke plume transmission discretization; s4, sampling meteorological conditions, and simulating smoke plume transmission; s5, calculating the radiation dose in the early stage of the grid domain, and carrying out risk assessment; s6, performing risk assessment on the health effect in the early stage of the grid domain; s7, calculating the medium-and-long-term stage radiation dose in the grid domain, and performing dose risk assessment; and S8, performing health effect risk assessment and accident consequence assessment in the medium-and-long-term stage. According to the method, the whole transportation process of the radioactive smoke plume under a serious accident is simulated, loss effects such as dry and wet settlement and radioactive decay of the smoke plume are considered, and the activity of the radionuclide deposited on the ground and retained in the air in the off-site space range is determined.

The present invention relates to an adaptive assessment method and apparatus for nuclear power plant component reliability, a storage medium, and an electronic device. The method comprises the following steps: constructing a Kriging initial model; gradually updating the Kriging initial model on the basis of first-layer samples of ICE to obtain a Kriging surrogate model; gradually updating the Kriging surrogate model on the basis of last-layer samples of the ICE; after the updating of the Kriging surrogate model is completed, obtaining a current Kriging model; and on the basis of the current Kriging model, assessing the reliability of a component to be assessed. In the present invention, first-layer adaptive Kriging gradually updates and explores a failure domain on the basis of the first-layer samples of the ICE until a set stopping criterion is satisfied, and on the basis of a currently constructed Kriging model, the last-layer samples of the ICE are also updated accordingly. Thus, it is ensured that an estimated failure probability converges unbiasedly to a real failure probability, and unnecessary updating of Kriging is avoided, thereby greatly improving calculation efficiency and saving calculation costs.

The invention discloses a nuclear power plant bolt installation method and system based on augmented reality, and belongs to the field of bolt intelligent installation, and the method comprises the steps: collecting nuclear power plant environment data based on an environment monitoring sensor, and obtaining environment adaptation parameters through anti-radiation reinforcement processing; generating an installation guidance sequence containing specifications and torque values based on the environment adaptation parameters and the bolt identification result; bolt image features in the installation guidance sequence are analyzed through an image processing algorithm, position and angle deviation indexes are extracted, and deviation calibration data are obtained; collecting a fastening torque signal based on a torque measurement sensor, and fusing the fastening torque signal and the deviation calibration data to obtain a torque deviation correction value; updating calibration parameters based on the torque deviation correction value, obtaining the corrected mounting position and angle, and determining the accuracy of the bolt in-position state; bolt surface defects and fastening degree characteristics are extracted through image analysis, and a bolt installation quality evaluation result is generated.

The invention provides a nuclear power regulation human factor trap identification method and device based on a knowledge graph, and the method comprises the steps: determining a current nuclear power regulation according to a to-be-executed task, and extracting an operation target in the current nuclear power regulation; on the basis of a pre-constructed interface knowledge graph, according to the current nuclear power regulation, calculating all regulation paths from a task starting point node to a task end point node; the interface knowledge graph takes interaction elements related to operation in the interface of the nuclear power plant simulator as nodes and takes the relationship between the interaction elements as edges; the task end node is an operation target; and obtaining a human factor trap identification result of the current nuclear power regulation according to a path structure in the regulation path. According to the method, the interaction elements in the nuclear power plant simulator interface are subjected to structured mapping through the interface knowledge graph, automatic recognition of the structural human factor trap in the nuclear power regulation can be effectively achieved, data support and logic basis are provided for regulation optimization and interface design, and finally safety risks caused by human errors are reduced.

The invention relates to a corrosion product deposition behavior numerical simulation analysis method and a related device, which are applied to a heat exchanger of a nuclear power plant residual heat removal system, and the method comprises the following steps: S1, establishing a three-dimensional geometric model corresponding to the heat exchanger based on a CFD platform; s2, performing grid division on the three-dimensional geometric model, setting boundary conditions and initial conditions of the three-dimensional geometric model, and establishing a thermal hydraulic model corresponding to the three-dimensional geometric model according to the grid division, the boundary conditions and the initial conditions; s3, calculating the thermal hydraulic model based on a FLUENT platform to obtain a temperature calculation result of a preset position of the heat exchanger; and S4, when the temperature calculation result meets the design value requirement, a corrosion product deposition and migration coupling model corresponding to the heat exchanger is established, and a sediment distribution result corresponding to the heat exchanger is calculated through the corrosion product deposition and migration coupling model based on the thermal hydraulic model. The method can predict the influence of corrosion product migration and deposition on the thermal performance of the heat exchanger.

The invention provides an anomaly diagnosis method for a nuclear power plant gamma energy spectrum continuous monitoring process, and the method comprises the following steps: S1, determining at least one target gamma characteristic peak which needs to be monitored under the current monitoring condition of a nuclear power plant, and calculating the anomaly of the target gamma characteristic peak based on the performance index of a gamma spectrometer and the expected energy of the target gamma characteristic peak; setting a parameter allowable range of each target gamma characteristic peak; the parameter permissible range at least comprises a peak center energy permissible range and a resolution permissible range; s2, acquiring a gamma energy spectrum output by the gamma spectrometer, and processing the energy spectrum to obtain actual measurement parameters of a target gamma characteristic peak; the measured parameters at least comprise a peak center energy measured value and a resolution measured value; s3, the actually measured parameters are compared with the corresponding parameter allowable ranges; and S4, if the actually measured parameter of any target gamma characteristic peak exceeds the corresponding parameter allowable range, determining that the state of the gamma spectrometer is abnormal. Automatic and real-time abnormity diagnosis of the monitoring state of the gamma spectrometer is realized.

The invention relates to the technical field of nuclear power plants, in particular to a nuclear power equipment operation defect grading method and device, electronic equipment and a storage medium. The invention provides a nuclear power equipment operation defect grading method, and aims to realize grading of nuclear power equipment operation defects through a systematic and multi-level fusion decision-making mechanism. The problems that rule grading lacks flexibility, graph grading is influenced by keyword sensitivity, large model grading field knowledge is insufficient, and precision and adaptability are limited due to the fact that a traditional fusion strategy is single in the prior art are effectively solved. The core of the method is that lexical meta processing and a value matrix mechanism are introduced, dynamic and fine-grained fusion of multi-base classifier output is achieved, and therefore the overall performance of a grading system is improved. Through lexical element processing, value matrix construction and dynamic updating and multi-classifier fusion decision making, the nuclear power equipment defect grading method with high precision, high adaptability and high reliability is realized, and many limitations in related technologies are effectively solved.

The invention provides a nuclear power plant safety system based on causal reasoning, and relates to the technical field of nuclear power plant safety monitoring and fault diagnosis. The nuclear power plant safety system comprises a multi-source sensing layer and a causal engine layer, the multi-source sensing layer is used for collecting operation parameters of a nuclear power plant, and the causal engine layer comprises a dynamic causal network construction module and an online reasoning module. The dynamic causal network construction module is used for constructing a dynamic causal network according to the operation parameters, a continuous causal edge generated based on an equipment physical equation and a discrete event edge generated based on a probabilistic safety evaluation event tree; and the online reasoning module is used for determining a key fault propagation path according to the dynamic causal network so as to locate a fault source. According to the method, the equipment physical equation is embedded into the dynamic causal network, so that the reasoning process is ensured to accord with thermal hydraulic and safety physical rules, the problem of high false alarm rate caused by correlation misjudgment in deep learning is avoided, and the safety of the nuclear power plant is improved.

The invention relates to the technical field of equipment life prediction, and provides a nuclear power plant equipment predictive evaluation and maintenance method and system based on self-attention, and the method comprises the steps: obtaining multi-source sensing data of equipment through a sliding window mechanism, and obtaining an input time window sequence after preprocessing; reasoning the time window sequence data through a model to obtain a state vector for regression analysis, and generating the residual service life of the equipment; performing visualization processing on the attention matrix to obtain an equipment health state interpretation map of the attention weight, and generating interpretation information; and fusing the obtained residual service life of the equipment and the corresponding interpretation information to generate an equipment maintenance strategy suggestion. According to the method, the sliding window and the Transform model are creatively fused, deep modeling and interpretability analysis of multi-source equipment data are achieved, and the equipment health state atlas is constructed based on an attention mechanism and used for accurate prediction and maintenance strategy generation.

The invention discloses a nuclear power plant instrument control system control algorithm simulation device and a simulation method thereof, and relates to the technical field of nuclear power plant instrument control software. The device comprises a user interface used for responding to user interaction operation, constructing a model structure of a control algorithm and receiving user input data as input data of the model structure; the code generation engine is used for analyzing the xml file corresponding to the model structure and obtaining source code implementation of a main operator of the model structure based on an analysis result; and the model entity is used for packaging and compiling the source code of the main operator to obtain an executable program of the model structure, executing the executable program based on the input data of the model structure to obtain a simulation result of the model structure, and sending the simulation result to the user interface for display. According to the device, the software verification process can get rid of dependence on embedded hardware equipment, and the software development and debugging efficiency is improved.

The invention provides a data management system for nuclear power plant probability safety evaluation, and relates to the technical field of nuclear power plants. The data management system comprises an original analysis module used for performing FMEA analysis, HRA analysis and reliability parameter analysis on a nuclear power plant, and synchronizing an FMEA analysis result, an HRA analysis result and a reliability parameter analysis result to an intermediate database module; the intermediate database module is used for generating basic event information and parameter information according to the FMEA analysis result, the HRA analysis result and the reliability parameter analysis result, and synchronizing the basic event information and the parameter information to the user module; and the user module is used for displaying the basic event information and the parameter information. Manual identification is not needed, the time of nuclear power plant probability safety evaluation early-stage data integration and data transmission is shortened, and the efficiency of probability safety evaluation analysis is improved.

The invention belongs to the technical field of nuclear power, and particularly relates to a nuclear power plant vibration measurement method and device based on a dynamic range technology. Comprising the following steps: sampling vibration signals after gain amplification by using a plurality of analog-to-digital converters with different measuring ranges to obtain an initial digital sequence; the initial digital sequence comprises a signal amplitude; performing amplitude region division on the initial digital sequence according to the magnitude of the signal amplitude to obtain a plurality of signal segments in different amplitude regions, and endowing the analog-to-digital converter with a target weight according to the saturation of the signal segments in the measuring range of each analog-to-digital converter; the saturation is the ratio of the signal amplitude to the upper limit of the measuring range of the analog-to-digital converter; the target weight comprises sub-weights respectively corresponding to a plurality of different signal segments of the analog-to-digital converter; and performing weighted fusion and splicing on the signal segments based on the sub-weights of the analog-to-digital converters in the different signal segments to obtain a target sampling signal.

The invention discloses a risk early warning method and system for an emergency diesel generator of a nuclear power plant, and the method comprises the steps: collecting operation parameters of a generator set in a hot standby state, and when the parameters are not in a preset normal range, indicating that the parameters are abnormal and the generator set breaks down; preprocessing the acquired operating parameters, and extracting effective features of the preprocessed operating parameters; on the basis of the generator set with the fault, combining with the effective characteristics, and utilizing a high-frequency data flow transient anomaly recognition algorithm to capture an anomaly type label to obtain fault information; evaluating the risk degree of the generator set according to the effective features and the abnormal type labels of the preprocessed operation parameters; and carrying out risk early warning and response on the generator set according to the risk degree of the generator set. According to the invention, the operation state of the emergency diesel generator set can be monitored in real time, accurate risk assessment and early warning information is provided, and the risk management capability of managers is enhanced.

The invention belongs to the technical field of nuclear power, and particularly relates to a nuclear power plant equipment coating heat conductivity coefficient prediction method and device. According to the model building disclosed by the invention, the common defects of pores and macroscopic horizontal cracks in the coating are considered, the coating is used as a tight skeleton, pore and crack three-phase composite system, and after one defect is gradually added into the substrate, the formed system becomes a new substrate in the next step. And repeating the compounding process until the two defects of pores and cracks are added into the system. Therefore, the actual operation state of the thermal barrier coating of the nuclear power equipment can be simulated more vividly. Furthermore, pore shape influence factors and crack shape influence factors corresponding to different porosities and crack rates can be determined through modeling and heat conductivity coefficient simulation calculation, and the actual heat conductivity coefficient of the coating is further predicted. And a theoretical basis is provided for researching the failure behavior of the service thermal barrier coating.

The invention discloses a hyper-parameter tuning method of a nuclear power plant neural network model and a related device, and belongs to the technical field of neural network hyper-parameter tuning. According to the hyper-parameter tuning method for the nuclear power plant neural network model, data preprocessing and hyper-parameter optimization of the neural network model can be considered, dynamic optimization is performed by incorporating the time sequence length into hyper-parameter combination, collaboration of data preprocessing and neural network model tuning is realized, and the robustness of the neural network model is improved. Therefore, the preposed process of data preprocessing, which is hyper-parameter optimization, is integrated into the overall optimization process to realize joint adjustment and optimization, so that the problem of splitting of data preprocessing and hyper-parameter optimization in the traditional method is solved, the overall optimization efficiency can be improved, the computing power consumption is reduced, and the overall optimization efficiency is improved. And the prediction precision and generalization ability of the time sequence prediction neural network model can be improved.

The invention belongs to the technical field of nuclear power plant power distribution system simulation, and aims to solve the problems of poor two-dimensional modeling intuition, low manual modeling efficiency, large error, single fault simulation dimension, insufficient visualization, difficulty in multi-source data integration, weak virtual-real linkage and the like in traditional DCS power distribution system simulation. The invention discloses a DCS power distribution system simulation system and method based on a virtual three-dimensional simulation technology. The system comprises a data layer, a logic layer and an application layer. According to the method, DCS power distribution system simulation is realized. According to the application, high-precision three-dimensional simulation, efficient fault simulation and visual display of the DCS power distribution system of the nuclear power plant are realized, and the operation and maintenance efficiency, the training effect and the fault handling accuracy are improved.

The invention belongs to the technical field of fluid control, and particularly relates to a system for predicting nuclear power plant valve opening and flow nonlinear sudden change. The preprocessing and mechanism analysis module is responsible for performing deep processing and consistency review on the data acquired by the sensor, and performing modeling and parameter correction on flow sections of different types of valves in combination with a physical mechanism; the data driving prediction module is responsible for performing XGBoost modeling and reasoning on historical and real-time collected multi-dimensional data on the basis of a physical mechanism analysis result, outputting a fine prediction value of the valve flow and providing a more sensitive response for a nonlinear abrupt change region; and the hybrid model fusion and adaptive updating module is responsible for organically fusing prediction results of the physical mechanism model and the XGBoost model, dynamically adjusting model parameters according to real-time operation data, and realizing high-precision prediction and stable control of the valve flow. According to the invention, real-time and high-precision prediction of non-linear abrupt changes possibly occurring in different opening degree intervals of the valve is realized.

The invention discloses a primary circuit washing and foreign matter checking method for a pressurized water reactor nuclear power plant. The primary circuit washing and foreign matter checking method for the pressurized water reactor nuclear power plant comprises the following steps: S10, obtaining the size and morphology of a foreign matter; s20, according to the flowing direction of the operation medium of the loop system, the size of the foreign matter and the intercepting area of the passing equipment, the pipeline where the foreign matter possibly flows through and the position of the equipment where intercepting is possible are obtained; s30, calculating the critical flow velocity of the foreign matter in the primary loop medium; s40, quantitatively judging possible paths and closure points of the foreign matters; and S50, determining a flushing path and a flushing flow according to the possible path and the interception point of the foreign matter. According to the primary loop flushing and foreign matter checking method for the pressurized water reactor nuclear power plant, the foreign matter can be effectively checked, and the checking efficiency can be improved.

The utility model discloses a nuclear power plant lifting type inspection device which comprises a device body and a pan-tilt camera mechanism, and the device body is provided with moving wheels. A controller is arranged in the device body, and an obstacle avoidance sensor connected with the controller is further arranged on the device body; the pan-tilt camera mechanism comprises a lifting support, a pan-tilt base and a pan-tilt camera, the lifting support is installed on the device body, the pan-tilt base is connected with the upper end of the lifting support, the pan-tilt camera is installed on the pan-tilt base, and a distance measuring sensor connected with the controller is further arranged on the upper surface of the pan-tilt base. The lifting type inspection device for the nuclear power plant can replace workers to inspect the nuclear power plant, the inspection efficiency is improved, the device body is provided with an obstacle avoidance sensor, the holder camera mechanism is provided with a distance measuring sensor, and space information around the lifting type inspection device for the nuclear power plant can be detected in multiple directions; the nuclear power plant lifting type inspection device is prevented from colliding with nuclear power plant equipment, and the nuclear power plant lifting type inspection device and the nuclear power plant equipment can be effectively protected.

A radiation monitoring system for a nuclear power plant, comprising: a radiation monitoring device (110); a central control platform (120) which is communicatively connected to the radiation monitoring device (110), wherein a data acquisition module (121), an analysis and determination module (122), and a warning and alert module (123) are provided in the central control platform (120); and a smart display terminal (130), which is communicatively connected to the central control platform (120). The data acquisition module (121) acquires monitoring information and parses same to generate parsed information; the analysis and determination module (122) performs statistical analysis processing on the parsed information to generate statistical analysis data, and generates an alert instruction when the statistical analysis data falls within a preset range; the warning and alert module (123) performs alert processing on the basis of the alert instruction and generates warning information; the smart display terminal (130) displays the warning information, and generates scheduled analysis reports on the basis of the statistical analysis data. Real-time monitoring of radiation of nuclear power plants is achieved.

The invention discloses a management method and system for improving the receiving rate of spare parts purchased in the engineering period of a nuclear power plant, and relates to the technical field of industrial automation and monitoring, and the method comprises the steps: extracting consumption records after commercial transportation for units of the same supplier in a group, generating a list of spare parts purchased in the engineering period, and removing low-failure-rate parts; high-frequency consumables are retained to improve pertinence. And secondly, for spare parts which are not present, not scheduled and wide in coverage, a framework protocol is established with a manufacturer to lock unit prices and agree on demand supply, so that inventory occupation caused by mass transfer is avoided. And finally, executing a four-consistency principle on the on-site spare parts, namely checking an EOMM manual, and finally confirming a list, spare part real objects and on-site installation real objects. When the model or the code is upgraded, the specification is upgraded and solidified in combination with the commitment function of the manufacturer and the EOMM manual; when differences occur, interchangeability argumentation is carried out through technical analysis and an item replacement process, spare parts which are argumented to be available are put in storage and updated to an equipment spare part BOM and a template work order, and verifiability, traceability and efficient receiving of the spare parts are achieved.

The invention belongs to the technical field of degassing membrane degassing devices of nuclear power plants, and discloses an assembly tool and an assembly method for a degassing membrane degassing device of a nuclear reactor. The assembly tool comprises a first tool body, a second tool body and a fastening assembly. Wherein the height of the portion, stretching into the end face of the outer shell, of the first pressing part is larger than the height of the portion, stretching into the end face of the outer shell, of the second pressing part, and the height of the second pressing part meets the requirement that when a final pressing position is reached, the second pressing part is pressed; the length of the part, extending into the outer shell, of the second pressing part is consistent with the length of the part, extending into the outer shell, of the gland assembly of the outer shell. The first tool and the second tool which are matched with each other achieve staged assembly of controllable pre-pressing, ejection ring mounting, symmetrical final pressing and precise centering on sealing assemblies at the two ends of the hollow fiber membrane column in the outer shell, and the good sealing effect is achieved.

The invention belongs to the technical field of reliability management of nuclear power plants, and particularly relates to a multi-focal-length visible light array cameras, a cooperative control unit and a central analysis platform, the multiple multi-focal-length visible light array cameras are located on the end side, and conversion from physical world real scenes to digital signal images is completed; the cooperative control unit is located on the side and is responsible for receiving, processing and analyzing data of the multiple multi-focal-length visible light array cameras, executing AI reasoning with high delay requirements, driving a holder and a lens to act and uploading related result data. The central analysis platform is located at a cloud side, gathers alarm data of all side devices, and carries out global situation presentation, historical data storage and backtracking, long-term trend analysis and multi-system linkage. The system has the beneficial effects that the tradeoff limitation among the view field, the distance and the precision in the prior art is overcome, and the industrial problem that the large view field cannot be considered is creatively solved through the cooperative working mode of the multi-focal-length optical array.

To provide a flying object protection facility and a nuclear power plant which can further suppress intrusion of a flying object, without being restricted by arrangement.SOLUTION: A flying object protection facility includes: a frame body having a plurality of frame members which are arranged around a protection object and are connected to each other; a plurality of net support parts which are fixed to the edge part of the opening of the frame body, and are arranged at an interval in an edge part extending direction; a protection net which is supported by the net support parts, closes the opening so as to spread in an in-plane direction of the opening, and is separated from the frame body at an interval in an out of plane direction perpendicular to the in-plane direction; and a gap filling member which is provided in the gap between the adjacent net support parts, and reduces the dimension in the out of plane direction of the gap.SELECTED DRAWING: Figure 4

The invention discloses a nuclear power plant distributed control system and control method, and relates to the technical field of nuclear power plant digital control, and the method comprises the steps: a global optimization layer generates a cross-unit general control strategy library based on a transfer learning algorithm according to the decision period of the global optimization layer; when the coordination control layer operates by using the transferable control strategy corresponding to the unit equipment where each two-loop subsystem is located, the corresponding two-loop subsystem control weight is dynamically allocated based on the multi-agent attention network according to the decision period of the coordination control layer; when the execution control layer operates by using the dynamically distributed two-loop subsystem control weight, the first-loop temperature, the first-loop pressure and the coolant flow are obtained according to the decision period of the control layer, a safety constraint matrix is calculated through a safety manifold projection module, and a quadratic programming problem with a relaxation factor is solved; and the corrected control weight of the two-loop subsystem is obtained and converted into a control instruction to be issued to a DCS field control station.