22 results about "Nuclear power industry" patented technology

The invention belongs to the technical field of nuclear power station file management, and particularly relates to an intelligent nuclear power station file classification and retrieval system based on artificial intelligence. The file acquisition module is responsible for uniformly acquiring and accessing multi-modal files in the nuclear power station; the preprocessing and natural language processing module is used for carrying out deep processing and semantic analysis on the collected multi-modal document; the dynamic classification module is used for carrying out multi-dimensional automatic classification on the multi-modal document based on a deep learning model and a nuclear power industry knowledge graph; the dynamic knowledge updating module is used for continuously monitoring new documents and user feedback and keeping adaptability to industry changes; the intelligent retrieval module is used for providing a query function for a user through semantic vectorization and a large-scale rapid retrieval technology; and the intelligent recommendation module is used for providing targeted document recommendation for the user through association analysis and collaborative filtering. According to the method, the problems of low classification efficiency, insufficient retrieval accuracy, weak dynamic adaptive capacity and limited multi-modal data processing capacity are solved.

The invention relates to the technical field of nuclear power data asset automatic management, in particular to a nuclear power digital twinning data warehouse structure system, which comprises a data processing layer, and is characterized in that the data processing layer reads original data of a nuclear power industrial internet platform, performs data standardization processing on the original data to obtain standard data, and sends the standard data to the nuclear power industrial internet platform; constructing a nuclear power industry theme library according to the standard data; the data integration layer performs data coding mapping, data classification and data fusion on the data of the nuclear power industry theme library to form a thematic library; the semantic enhancement layer marks the data of the nuclear power industry theme library and the data in the thematic library formed by the data integration layer, and constructs a structured feature tag library for the data associated with feature tags; the analysis application layer reads data of the feature tag library, and constructs a digital twinborn algorithm library and a digital twinborn sample library through algorithm analysis and sample training. The system supports equipment operation and maintenance from regular maintenance to predictive maintenance based on bottom support and four-layer progressive architecture of a nuclear power industrial internet platform.

The invention belongs to the technical field of nuclear power data processing, and particularly relates to a multi-level data cleaning method for the nuclear power industry. Comprising a first hierarchy data importing and preprocessing layer, and the first hierarchy is a basic unit for nuclear power multi-hierarchy data cleaning; the second level carries out local processing layer data processing, and the data subjected to secondary cleaning is recompressed, feature codes are extracted, and then the data are transmitted to the third level; or directly forwarding the unprocessed original compressed data; the third hierarchy carries out data processing of the platform layer in the data; and the fourth level performs data processing of the data application layer, and is responsible for performing persistent storage on the data according to a standardized format after the data is subjected to full-process cleaning, compression, feature extraction and desensitization processing. The method has the beneficial effects that the method is specially customized for the nuclear power industry: special requirements of high confidentiality, network isolation, large data volume and the like of data in the nuclear power industry are fully considered, and a special cleaning and desensitization process is designed.

The invention relates to the technical field of oxygen cleaning in sealing cavities in the nuclear power industry, and discloses an irradiation-resistant concentric double-channel one-way valve which comprises a concentric double-channel one-way valve body and a concentric double-channel exhaust pipe, and the concentric double-channel one-way valve body comprises a mounting seat, an inner valve seat and a top adjusting cap. The concentric double-channel exhaust pipe comprises a center channel and an annular channel, a bottom body through hole is formed in the bottom of the mounting seat, a first channel is formed in the inner valve seat, and a second channel is formed in the inner valve seat. Through the design of the center channel and the annular channel of the concentric double-channel exhaust pipe and the cooperation of the rapid butt joint structure of the first conical surface rapid connector and the second conical surface rapid connector, complete independent separation of an air inlet channel and an air exhaust channel is achieved, argon can accurately enter a sealing cavity through the center channel, replaced oxygen is efficiently exhausted through the annular channel, and therefore the sealing effect is improved. A closed circulation loop is formed, the gas replacement efficiency of the sealed cavity is greatly improved, and it is ensured that oxygen in the cavity is rapidly and thoroughly cleaned.

The application belongs to the technical field of digitalization and intelligent application in nuclear power industry, and provides an intelligent diagnosis and compliance automatic checking system and method for maintenance regulations of a nuclear power plant, the system comprising a rule base management module, an intelligent analysis module, a rule engine module and a user interaction module, the method creating and maintaining a machine-readable rule base for checking maintenance regulations of a nuclear power plant, acquiring and analyzing a maintenance regulation file to be checked, generating a structured regulation object model, matching and evaluating the regulation object model with rules in the rule base, generating a diagnosis result set, displaying the diagnosis result set to a user, and providing interactive modification guidance.The application performs automatic and real-time compliance checking and logic diagnosis on maintenance regulations of a nuclear power plant, so as to replace most repetitive and rule-based manual review work with machine automatic checking.

The invention discloses a configuration file synchronization method and system for a double-CPU redundant PLC in the nuclear power industry. The method comprises the steps that S1, one CPU is set to be in a master CPU mode, and the other CPU is set to be in a slave CPU mode; the two CPUs respectively comprise a configuration file; s2, the CPU in the slave CPU mode downloads the configuration file from the CPU in the master CPU mode and synchronizes the configuration file; and S3, when one CPU is restarted, updating the master-slave state according to a preset rule and synchronizing the configuration file. According to the configuration file synchronization method and system for the double-CPU redundant PLCs in the nuclear power industry, the configuration file consistency between the master PLC and the slave PLC can be better guaranteed.

The application belongs to the field of natural language processing in the nuclear power industry, and particularly relates to a professional word segmentation method applied to nuclear power industry corpus, which comprises nuclear power professional vocabulary construction, nuclear power stop word vocabulary construction, nuclear power synonym vocabulary construction, nuclear power same pronoun vocabulary construction, nuclear power field new word recognition, nuclear power field entity automatic recognition, nuclear power field synonym automatic recognition, nuclear power corpus Chinese accurate word segmentation and the like operations. The application has the beneficial effect of completely solving the problem of inaccurate Chinese word segmentation of nuclear power industry corpus, laying a solid foundation for the application of subsequent big data and artificial intelligence in the field of nuclear power natural language processing, and reducing the investment of other practitioners in the field of nuclear power in natural language processing.

The invention relates to the field of nuclear power industry automation, in particular to a nuclear power operator monitoring optimization method and system based on an artificial intelligence technology. The method comprises the following steps: collecting operation data of each system of the nuclear power station; constructing a deep learning prediction model by adopting a fusion architecture of a long short-term memory network and a generative adversarial network; the deep learning prediction model is used for automatically detecting abnormal events; according to an output result of the deep learning prediction model, constructing an intelligent risk assessment system, and performing comprehensive risk rating on the abnormal event; automatically generating early warning information according to the comprehensive risk level of the abnormal condition, and pushing the early warning information to a nuclear power station operator in real time to ask the operator to confirm; the deep learning prediction model is continuously updated according to a self-learning and feedback learning mechanism. According to the method, the problems of leakage, misjudgment and the like possibly occurring when the operator monitors the disk under complex working conditions and mass data are reduced, the disk monitoring efficiency of the operator of the nuclear power station is improved, and safe and stable operation of the nuclear power station is ensured.

The present application belongs to the field of instrument and control, and relates to a non-direct measurement type wind speed meter and a wind speed measurement method. The non-direct measurement type wind speed meter comprises a wind speed meter device shell, a data processing circuit arranged in the device shell, a propeller type wind speed sensor and a cable arranged on the device shell, the propeller type wind speed sensor and the cable being in data connection with the data processing circuit, and a touch screen, a charging interface and a switch button also being arranged on the device shell. The present application has the following remarkable effects: reducing the hidden danger of operation safety of hoisting equipment without being equipped with a wind speed meter, using on the ground, calculating the wind speed at the hoisting work height according to the wind speed data at the ground, measuring accurately and quickly, improving work efficiency, improving unit profit, improving quality and efficiency, and having popularization value in the nuclear power industry and engineering construction hoisting, high-altitude maintenance operation occasions.

The invention belongs to the technical field of computer application, and particularly relates to a cloud and edge integrated time sequence data processing system. Deploying a power plant side time sequence database in each power plant, and collecting and storing time sequence data of each power plant in a local time sequence database of the power plant; a center side time sequence database is deployed in the data center, and the power plant side time sequence database is uploaded and accessed to the center side time sequence database according to needs; and deploying a time sequence data processing system, and performing unified management on the power plant side time sequence data and the center side time sequence data. Efficient management and service of the time series data of the nuclear power industry internet platform are achieved, the time series data management efficiency is improved, the data service quality is improved, and the data use threshold is reduced.

This invention belongs to the field of nuclear power industry technology, specifically relating to the demineralized water production and deoxygenation system and control method during the initial start-up phase of a nuclear power plant. The system includes a clean water pump, a clean water pump and a clean water pump outlet manual valve connected by a pipeline, a clean water pump outlet manual valve and an activated carbon filter connected by a pipeline, an activated carbon filter and a cation exchange bed connected by a pipeline, a cation exchange bed and a vacuum degassing tower level regulating valve connected by a pipeline, a vacuum degassing tower level regulating valve and a vacuum degassing tower connected by a pipeline, a vacuum degassing tower and an intermediate water pump connected by a pipeline, an intermediate water pump and an intermediate water pump outlet valve connected by a pipeline, an intermediate water pump outlet valve and an anion exchange bed connected by a pipeline, an anion exchange bed and a first regeneration air pressure isolation valve connected by a pipeline, an anion exchange bed and a mixed bed connected by a pipeline, a mixed bed and a second regeneration air pressure isolation valve connected by a pipeline, a mixed bed and a primary loop inlet water supply valve connected by a pipeline, a primary loop inlet water supply valve and a primary loop water supply tank connected by a pipeline, a primary loop water supply tank and a primary loop water supply outlet valve connected by a pipeline, and a primary loop water supply outlet valve and a primary loop water supply pump connected by a pipeline. The beneficial effects of this invention are as follows: by modifying the facilities and changing the operation mode of the original demineralized water production system, the system can achieve fully automatic and stable production of deoxygenated water, solving the problem of not being able to provide a large amount of deoxygenated water during the initial start-up.

This invention discloses a nuclear power industry mechanism model platform architecture for integration with an industrial internet platform, comprising a runtime environment layer, a service layer, an interface layer, a view layer, and an application layer. The runtime environment layer abstracts the hardware, provides the necessary library files for the upper-layer environment, and handles inter-cluster scheduling and communication. The service layer includes AI models, real-time computing models, cloud simulation models, industrial cloud software models, auxiliary analysis tools, and integrated development and execution tools. The interface layer standardizes and uniformly manages the interfaces of the service layer. The view layer includes mechanism model library interfaces, an operation management module, a data management module, and an engineering management module. The application layer includes artificial intelligence application scenarios, real-time computing scenarios, cloud simulation scenarios, and cloud-based industrial software scenarios. This invention provides an integrated development and execution environment for nuclear power industry mechanism models.

The invention discloses a double-CPU redundant PLC master-slave switching method and system for the nuclear power industry. The method comprises the steps that S1, when two CPUs are powered on, the two CPUs continuously monitor the heartbeat of each other; s2, according to a first preset rule, one CPU is set to be in a master CPU mode, and the other CPU is set to be in a slave CPU mode; s3, the CPU in the slave CPU mode actively synchronizes the application program of the CPU in the master CPU mode; s4, the CPU in the master CPU mode synchronizes state data and operation data to the CPU in the slave CPU mode; and S5, when one CPU is abnormal or reset, the two CPUs run after switching the master-slave mode states according to a second preset rule. According to the double-CPU redundant PLC master-slave switching method and system for the nuclear power industry, when the master CPU breaks down, the other CPU can be immediately switched to enter the master CPU mode to work, and the switching reliability of the system can be guaranteed.

The invention provides a trend curve generation method and device and electronic equipment, and relates to the technical field of man-machine interface trend display. The method comprises the steps of obtaining corresponding target data according to a preset display demand; determining a data type of the target data; generating a corresponding target trend curve according to the data type and the target data; wherein if the data type is a switching value, the target trend curve displays a signal flipping feature corresponding to the target data; and if the data type is an analog quantity, the target trend curve displays an extreme value feature corresponding to the target data. According to the method, if the data type is a switching value, the target trend curve displays the signal flipping feature corresponding to the target data; if the data type is an analog quantity, the target trend curve displays an extreme value feature corresponding to the target data. Therefore, the trend curve keeps the data characteristics, the data distortion condition is reduced, and the detailed analysis requirement of the nuclear power industry on the signal data can be better met.

The utility model provides a high-temperature air valve leakage rate detection device, which comprises a pressure stabilizing box, a heating box, an electric heater, a temperature sensor, a pressure sensor and the like, and realizes accurate quantitative detection of the leakage rate of a valve by simulating a high-temperature environment of + 400 DEG C to + 800 DEG C and combining a temperature control system. The problem that a traditional method cannot adapt to a high-temperature environment and cannot achieve accurate measurement is solved, the method has the advantages of being easy and convenient to operate, safe and reliable, the internal and external leakage rates of valves of different specifications can be effectively detected, and important technical support is provided for the nuclear power industry. In addition, a variable-frequency control fan, a high-precision flow meter, a graphite packing and the like are adopted, so that the stability and the sealing performance in the test process are ensured.

The invention discloses a method for repairing a renovated heat shield of a hydraulic component of a main pump of a nuclear power plant, which comprises the following steps of: accurately controlling the dimensional accuracy of the matching surfaces of the heat shield, a diffuser, a sealing chamber and other components through a process of systematically detecting the run-out value of multiple reference surfaces and carrying out feed turning for three times, and ensuring the overall dimensional chain requirement. And high-precision self-repairing of the heat shield is realized. The performance of the repaired heat shield reaches the international excellent level, the safety risk and cost of delivery maintenance of high-radioactivity equipment are remarkably reduced, and important technical support is provided for autonomous maintenance of key equipment in the nuclear power industry.

This utility model discloses a reverse osmosis test device for nuclear power industry wastewater, including a main frame consisting of a horizontally arranged chassis and a support. A high-pressure pump is mounted on the chassis, and a reverse osmosis membrane is detachably mounted on the support. The outlet of the high-pressure pump is connected to the inlet of the reverse osmosis membrane via a pipe. The clear water outlet of the reverse osmosis membrane is connected to a pipe, and the high-concentration water outlet of the reverse osmosis membrane flows back to the inlet of the reverse osmosis membrane via a pipe. The reverse osmosis membrane is connected to the pipe via a quick-release connecting device. Roller components are provided at the bottom of the chassis. This utility model allows for the replacement of different models of reverse osmosis membranes, facilitating multiple tests with different models of reverse osmosis membranes based on varying raw water data requirements. Furthermore, the reverse osmosis membrane is easy to install and remove, and the operation is simple.

The invention belongs to the technical field of nuclear power industry internet platform optimization, aims to solve the problem that a nuclear power industry mechanism model lacks an integrated development environment, and discloses a nuclear power industry mechanism model integration platform which comprises an operation environment layer, a service layer, an interface layer, a view layer and an application layer. The operation environment layer is used for providing library files for an upper-layer environment and carrying out scheduling and communication among clusters, the service layer is used for carrying out unified management, scheduling and operation on various mechanism models and tools, and the interface layer is used for carrying out standard packaging and unified management on interfaces of the service layer. The view layer is used for presenting a complex model capability and a data processing process of a bottom layer, and the application layer is used for providing an artificial intelligence application scene, a real-time computing scene, a clouded simulation scene and an industrial clouded software scene which are quickly constructed based on lower-layer services. According to the application, an integrated development operation environment is provided, and an online arrangement and debugging operation environment and a service packaging and publishing function are provided for four components of a service layer.

The present application belongs to the field of instrument and control, and relates to a kind of control cabinet signal terminal detection device.A kind of control cabinet signal terminal detection device, wherein, including device shell, data processing device is arranged in device shell, host computer signal line interface is arranged on device shell, host computer signal line interface is electrically connected with interface module, and the signal of interface module is sent to data processing device, and touch screen is also arranged on device shell.The remarkable effect of the present application is: the application of the device can improve the debugging and maintenance efficiency of the control cabinet, in the field of nuclear power, can improve the unit income, reduce the repeated physical labor, reduce the personnel cost, achieve the effect of "reducing cost and increasing efficiency", and has popularization value in the nuclear power industry and other industries that use a lot of control cabinet.

The application discloses borosilicate glass and a preparation method and application thereof. High radioactive waste liquid produced by nuclear power industry has great environmental risk and must be treated safely and reliably. Borosilicate glass is widely used as base glass for solidifying high radioactive waste liquid in the international society. However, the solubility of molybdenum in the borosilicate base glass is low, which leads to the problem that molybdate yellow phase is easily separated out in the solidified body glass. The application adjusts the composition of the borosilicate glass to obtain the base glass with high molybdenum inclusion rate. Specifically, firstly, B2O3 is gradually replaced by Al2O3 to obtain the optimal composition that can add 8mol% of MoO3 without crystallization. On the basis, Li2O is used to replace Na2O and CaO, and the molar ratio of Na2O to CaO is kept unchanged in the process to obtain the borosilicate glass that can add 11mol% of MoO3 without crystallization. The phenomenon that the high radioactive nuclear waste has low inclusion rate in the glass solidification process is improved.

The invention discloses a low-latency data security transmission method and device for the Internet of Things of the nuclear power industry, and the method comprises the following steps: S1, segmenting collected data according to a data segmentation strategy, and carrying out the group signature of each segmented block data; step S2, compressing the block data, performing encryption preprocessing after establishing transmission connection, and executing residual encryption processing during data transmission; s3, the sending end sends the encrypted ciphertext, and the encrypted ciphertext is sent to the receiving end through different paths according to the pseudo-random table; and S4, performing data reduction on the received data, and constructing a layered integrity verification architecture to perform integrity verification on the received data. The method has the technical effects of high data transmission security and low time delay.

The invention relates to the technical field of stainless steel forging, in particular to a forging method of a nitrogen-controlled austenitic stainless steel forge piece for nuclear power. A forging method of a nitrogen-controlled austenitic stainless steel forge piece for nuclear power comprises the following steps that smelting is conducted, specifically, a Z2CND18-12 electroslag steel ingot is smelted through an argon-oxygen decarburization furnace and the like, and the mass percent of all chemical components is accurately controlled; forging: after cogging the electroslag steel ingot, heating to 1150 + / -10 DEG C according to specific parameters, preserving heat for 1.5 hours, and then forging and deforming to obtain a rough forging; treatment: carrying out solid solution heat treatment, sampling and carrying out transverse physical and chemical property inspection; and finally, machining to the required size, and then carrying out nondestructive inspection, appearance size inspection and finished product identification in sequence. The preparation method is accurate in material component control, the intergranular corrosion risk is reduced, and various properties are improved; the forging process adopts composite smelting, specific parameter setting, multi-step cooperation, total forging ratio greater than 8 and solid solution heat treatment, so that the quality of the forged piece is integrally improved, and the harsh requirements of the nuclear power industry are met.