2381 results about "Nuclear power" patented technology

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

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

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

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

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

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

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

The utility model relates to a nuclear power high-radiation object containing device and containing and transferring equipment. The containing and transferring equipment comprises the nuclear power high-radiation object containing device. The nuclear power high-radioactivity storage device is specially designed for underwater operation, and can safely store and seal high-radioactivity waste under the condition that normal operation of a reactor is not affected. The sealing mechanism ensures that the radioactive substance storage space is completely sealed in the transferring and long-time storage process, radioactive substances are prevented from leaking, and the safety of the treatment process is greatly improved. And secondly, the torque input end allows torque to be input through an external tool to achieve rotation of the lock cylinder, so that the closing or opening action is rapidly and effectively completed, the operation process of containing and closing the radioactive substances is simplified, and the containing and closing efficiency of the radioactive wastes is improved.

The invention discloses a containment failure probability curve fitting method and system based on a random forest, and relates to the technical field of nuclear power safety. Comprising the following steps: acquiring key parameters influencing ultimate bearing capacity of a containment, determining a distribution interval of the key parameters, and establishing a key parameter table; performing finite element calculation on the basis of the key parameter table, obtaining ultimate bearing capacity of the containment vessel under different parameter combinations and temperature loads, and establishing a database; performing normalization preprocessing on the database to form a training data set; establishing a random forest model and performing regression model training by using the training data set; inputting actual design parameters of the containment and the temperature required to be evaluated into the trained model to obtain an ultimate bearing capacity predicted value of the containment; and fitting of a failure probability curve is carried out based on the central limit theorem. According to the method, complex probabilistic safety analysis is converted into a standardized calculation task, and the implementation threshold of nuclear power plant design verification and safety review is greatly reduced.

The invention relates to the technical field of metal smelting, and particularly discloses a preparation method of a high-purity IN718 alloy material. According to the method, on the premise that the mechanical property result redundancy of the IN718 alloy material is large, the content of inclusions and formation of carbides in the steelmaking process are reduced by optimizing the content of C, N and Nb elements in the vacuum induction melting process, reducing the refining temperature and reducing the melting speed of vacuum self-consuming remelting; and in cooperation with two-heating-number upsetting and drawing deformation in the forging process, the situation that carbides in the IN718 alloy material are dispersed unevenly due to segregation is avoided. According to the high-purity IN718 alloy material and the preparation method thereof, the content of carbides in steel ingots is remarkably reduced by controlling all parameters in the duplex process, the overall level of the carbides in the high-purity IN718 alloy material is smaller than or equal to 2.0 level after homogenizing diffusion annealing, forging, machining and heat treatment, the purity of the existing IN718 alloy material is improved, and the use requirements of special equipment such as deep sea equipment and nuclear power equipment can be met.

The invention belongs to the technical field of special maintenance of reactor bodies, and particularly relates to an electric spark machining head for cutting a sleeve flange in a narrow space. Comprising an expansion mechanism, a fine adjustment jacking mechanism, a rotating mechanism, an electrode and a radial servo feeding mechanism, the rotating mechanism provides rotary motion of the electrode and drives the electrode to conduct rotary machining, the radial servo feeding mechanism provides radial feeding motion of the electrode, and the expansion mechanism plays a role in fixing and positioning. The fine adjustment jacking mechanism drives the rotating mechanism, and the radial servo feeding mechanism drives the electrode to do up-down, rotating and radial feeding movement. The method has the beneficial effects that the damage to the pressure-bearing boundary of the primary loop of the nuclear power unit can be avoided under the condition that the heat sleeve is worn out of limits and needs to be replaced aiming at the common problem of wear settlement of the heat sleeve of the control rod driving mechanism of the nuclear power unit, and the whole dismantling work has relatively high safety, reliability and economical efficiency; and greater benefits can be created for the operation of a power plant.

The invention relates to the technical field of transportation and storage, and discloses a nuclear power fuel transportation device for a nuclear power station, the nuclear power fuel transportation device comprises a supporting plate, an adjusting mechanism is arranged above the supporting plate, and an inflation mechanism is arranged above the supporting plate; the adjusting mechanism comprises a shell, the bottom face of the shell is fixedly connected with the upper surface of the supporting plate, the inner wall of the shell is rotationally connected with four rotating columns, and the outer surface of each rotating column is fixedly connected with a gear. According to the nuclear power fuel transporting device for the nuclear power station, by arranging the adjusting mechanism, the adjusting mechanism achieves flexible adjustment of the supporting range angle of the transporting device through a linkage structure of a gear, a rack and a hydraulic rod, and when the hydraulic rod drives the rack to move up and down, the rack drives the gear and a rotating column which are meshed to rotate synchronously; by means of the design, the supporting range can be adjusted in real time according to the topographic features of a transportation environment such as a narrow channel and a concave-convex road surface.

The embodiment of the invention provides a method and a device for determining thermal safety margin of a reactor core, and belongs to the technical field of nuclear power. The method comprises the steps that initial information of various fuel assemblies in a reactor core is obtained, and the initial information comprises stirring and mixing grillwork geometric characteristics of the fuel assemblies and test results obtained by conducting a critical heat flux density test on the fuel assemblies; determining a target critical heat flux density relational expression corresponding to the reactor core according to the initial information of the multiple fuel assemblies; and performing thermal safety margin calculation on the reactor core according to the target critical heat flux relational expression to obtain a target thermal safety margin. According to the embodiment of the invention, the problem of low accuracy of thermal safety margin calculation of the reactor core in the prior art can be solved, the characteristic difference of different types of fuel assemblies is fully considered, and the accuracy of a thermal safety margin analysis result is improved.

The invention discloses a power coordination control method of a high-temperature gas cooled reactor nuclear steam supply system, which relates to the technical field of nuclear power, and comprises the following steps of: coupling multiple modules in the high-temperature gas cooled reactor nuclear steam supply system through a common conventional island; the key state parameters of the to-be-adjusted module are used as main control variables, and the other modules are used as auxiliary control variables, so that the mutual influence relationship among the modules can be comprehensively considered; reasoning the control quantities based on a preset fuzzy rule to determine a fuzzy control strategy, so that adverse effects among modules can be counteracted, overall parameters are kept in a design value range, and safe and stable operation of the system is guaranteed; flexible adjustment can be performed according to key state parameters of different modules by using a fuzzy control strategy, the power of the reactor is quickly and accurately controlled, the dynamic response capability of the system is improved, and the requirement that the power of the reactor is quickly adjusted along with the load requirement of the steam turbine generator unit is met.

The invention relates to the technical field of pipeline decontamination, in particular to an online pipeline ultrasonic decontamination device and method suitable for various pipe diameters, and the online pipeline ultrasonic decontamination device comprises a numerical control generator, a transducer, an amplitude-change pole, an adaptive clamp, an online monitoring device and other key components. And through the designed adaptive clamp, the device can act on pipelines with various pipe diameters and can move along the pipelines, and the decontamination requirements in different scenes are met. The online ultrasonic decontamination device is suitable for maintenance and cleaning work of pipelines with different pipe diameters in nuclear power facilities, and has important significance in improving the safety of the nuclear facilities and guaranteeing radiation protection for operators. The problem that an ultrasonic device is poor in applicability is effectively solved, meanwhile, the flexibility of the device is guaranteed, effective online decontamination of pipelines with various pipe diameters can be achieved through a single set of device, the decontamination cost of radioactive contamination of nuclear facility pipelines is effectively reduced, online efficient decontamination of radioactive contamination deposited in the pipelines is achieved, and the service life of the pipelines is prolonged. The safe and stable operation of the reactor is ensured, and the radiation risk of operators is reduced.

The invention provides a nuclear power safety analysis report examination method and an applicable system and a readable medium thereof, and relates to the technical field of nuclear power. The review method comprises the following steps: converting each design file into document fragment data through a knowledge maintenance agent, and storing the document fragment data into a knowledge base; converting the nuclear power safety analysis report into a plurality of to-be-examined text blocks through a document analysis agent; extracting at least one technical expression statement and a corresponding retrieval problem and a matched knowledge fragment from each to-be-examined text block through a retrieval composite agent; performing consistency judgment on each technical expression statement, and a retrieval problem and a matched knowledge fragment corresponding to the technical expression statement through a technical review agent to obtain initial review data; and obtaining a final examination decision agent and a historical examination database, and generating corresponding final examination data through the final examination decision agent according to the historical examination database and the initial examination data.

The invention provides a nuclear power station operation optimization method and system, electronic equipment and a storage medium. The nuclear power station operation optimization method comprises the steps of classifying acquired historical operation data and real-time operation data of a nuclear power station; inputting high-security-level and strong-real-time data obtained from a data classification result into an AI algorithm module, and inputting obtained non-real-time data or unstructured data into a large model module; the AI algorithm prediction result and the large model prediction result are subjected to tradeoff fusion processing, and a fault detection result of the nuclear power station is obtained; inputting a fault detection result into a nuclear power station analog machine for operation; and optimizing the operation of the nuclear power station based on the simulation operation result. According to the invention, the AI algorithm module and the large model module are combined, the simulation operation result is obtained by combining the nuclear power station simulator, and the operation of the nuclear power station is optimized based on the simulation operation result, so that the intelligent decision-making capability is improved, the verification cost is reduced, and a closed-loop iterative optimization system is constructed.

The invention discloses a bidirectional visible narrow rectangular flow channel CHF test device and test method, and belongs to the field of nuclear power. The bidirectional visible narrow rectangular flow channel CHF test device comprises a pressure-bearing module and a transparent heating module, the pressure-bearing module comprises a pressure-bearing frame, a rectangular flow channel is arranged in the pressure-bearing frame, and through observation windows are arranged on the two sides of the pressure-bearing frame; the transparent heating module comprises a transparent heating assembly and a power supply module, the transparent heating assembly is installed on the observation window in a sealed mode and defines a test space, the transparent heating assembly comprises an ITO transparent conducting film plated on an ITO transparent conducting film substrate, and the transparent heating assembly provides heat input and a visible observation area in the CHF test. The test device can provide bidirectional visible CHF test conditions and effectively improve the test observation precision.

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 belongs to the technical field of vertical jacking of underwater shield tunnels, and particularly relates to a submarine hard rock shield tunnel nuclear power cold source drainage head construction method which comprises the following steps: reinforcing a sludge layer between seawater and a rock stratum; a pile casing is installed in the reinforcement treatment area of the sludge layer; bed rock in the pile casing is removed; the pile casing is backfilled with a sealing material; performing protection treatment on the outer side area of the pile casing; and shield tunneling construction is conducted in the rock stratum, a tunnel is formed, and vertical jacking construction is conducted on the sealing material in the pile casing through the tunnel to form a drainage head. According to the method, the key technology related to subsea tunnel shield internal drainage head construction under the hard rock condition can be achieved; the problems of hard rock treatment and backfilling compaction at the vertical jacking part are solved, the treatment area is reduced to the maximum extent, the cost is saved, the construction progress is accelerated, the construction safety is guaranteed, normal tunneling of slurry balance shield tunneling is guaranteed, and meanwhile the requirement of vertical jacking for the stratum is met.

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 belongs to the technical field of nuclear power, and particularly relates to a device and method for relieving remote expansion of a cushion block locking cap of a heat insulation sleeve. Comprising a locking cap expansion device and a long rod, the long rod is used for remote operation above a pool, and the locking cap expansion device comprises a positioning pin, a positioning cylinder, a clamping gripper, an aligning and screwing operation head, an expansion head and a pressing expansion operation head. The device has the beneficial effects that a long-distance long rod is adopted to operate screwing positioning alignment and pressing expansion, and remote operation of locking of the cushion block locking cap is achieved. A special device integrating positioning of an expansion tool, screwing positioning of an expansion head, clamping and fixing and pressing expansion is adopted, underwater remote expansion integrated operation of the relieving cushion block locking cap is achieved, and the process steps are simplified.

The invention belongs to the technical field of nuclear power station maintenance management, and particularly relates to a nuclear power maintenance decision-making system and method based on multi-Agent cooperation. The system comprises an input layer, a multi-Agent cooperation layer, a knowledge support layer, a decision processing layer, an output and interaction layer and a feedback learning layer. The input layer receives initial work order information including equipment basic information and fault description; the multi-Agent collaboration layer allocates sub-tasks to predefined six types of professional Agents according to work order information and completes information interaction; the knowledge support layer comprises a nuclear power professional knowledge base, a historical maintenance database and a rule and regulation library; the decision processing layer performs conflict detection, negotiation and decision fusion on Agent output; the output and interaction layer provides a decision result display and man-machine interaction interface; and the feedback learning layer realizes comprehensive improvement of nuclear power maintenance decision-making efficiency and safety. The method has the beneficial effects that a multi-professional Agent collaborative network technical means is adopted, and the technical effects of maintenance decision cross-professional information instant sharing and efficient collaboration are realized.

The invention relates to the technical field of nuclear power construction, in particular to a tensioning jack with a three-layer automatic locking tool anchor and a using method thereof.The tensioning jack comprises an oil cylinder, the right end of the oil cylinder is in threaded connection with an end cover, and a sealing plate is fixedly installed at the end, located on the inner side of the oil cylinder, of the end cover and is in sealed connection with the inner wall of the oil cylinder; the right end of a center penetrating sleeve is fixedly connected between the end cover and the sealing plate, the left end of the center penetrating sleeve extends into the left side of an inner cavity of the oil cylinder, a piston is slidably connected into the oil cylinder in a sealed mode, and the right side of the piston sleeves and is slidably connected to the outer wall of the center penetrating sleeve in a sealed mode. A second oil cavity is formed between the outer wall of the piston and an inner cavity of the oil cylinder, a three-layer automatic locking tool anchor assembly used for automatically anchoring the prestressed steel strand is arranged on the left side of the inner wall of the center penetrating sleeve, and an automatic anchor withdrawing assembly is arranged at the left end of the piston. According to the tensioning jack and the using method thereof, operation is easy and fast, and the tensioning efficiency can be 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 radiation-resistant protective cable for a nuclear power station and a preparation method thereof, and belongs to the technical field of cables, the radiation-resistant protective cable for the nuclear power station comprises a cable body and a sheath layer, and the sheath layer comprises the following components in parts by mass: 100 parts of polypropylene resin, 20-40 parts of ethylene propylene diene monomer and 5-12 parts of modified multi-walled carbon nanotubes. 8-15 parts of a heat conduction enhancer, 2-6 parts of an antioxidant, 1-3 parts of a heat stabilizer and 4-8 parts of a plasticizer; the heat conduction reinforcing agent is prepared by carrying out surface modification on composite powder of aluminum nitride and boron nitride through a silane coupling agent. Through the synergistic effect of the modified multi-walled carbon nanotubes and the surface modified heat-conducting enhancer, the heat-conducting property, radiation resistance and heat stability of the cable are remarkably improved on the premise of keeping excellent electrical insulation property.