413 results about "Nuclear industry" patented technology

The invention discloses a nuclear industrial robot body intelligent system based on a large model, which realizes autonomous sensing, decision making and execution of a robot in a nuclear industrial environment by integrating a sensing module, a learning model module, an execution module, a communication module and a security module. The sensing module adopts a multi-sensor fusion technology to collect environmental data such as temperature, radiation intensity and gas concentration in real time; the decision-making module dynamically generates a task execution strategy based on an open source large model base in combination with deep learning and reinforcement learning algorithms; the execution module completes complex tasks such as equipment maintenance, fault processing and nuclear waste carrying through a high-precision mechanical arm and a force feedback control technology; the communication module supports data interaction between the robot and a control center, and remote monitoring and emergency intervention are achieved; the safety module monitors the state of the robot in real time, multiple safety protection mechanisms are provided, and stable operation of the robot in the high-radiation environment is ensured. According to the invention, the operation efficiency and safety of nuclear industry facilities are obviously improved.

The invention relates to the technical field of data processing, and discloses a thinking instruction data generation method and system, electronic equipment and a storage medium, and the method comprises the steps: integrating a multi-source heterogeneous nuclear industry data corpus, and forming a standardized data source; thinking chain instruction data are constructed through an instruction generation framework driven by a large language model, multi-level security constraint processing is performed on the thinking chain instruction data, and contents which do not conform to nuclear industry security specifications are identified and eliminated; executing multi-dimensional quality evaluation on the thinking chain instruction data passing the security constraint, and removing the thinking chain instruction data which does not reach a quality threshold value; and performing real-time updating and dynamic optimization on the nuclear industry data corpus and the thinking chain instruction data based on newly collected nuclear industry field data. The method can improve the flexibility, accuracy and timeliness of instruction generation.

The invention relates to a crown ether covalent organic framework material as well as a preparation method and application thereof. The preparation method comprises the following steps: dissolving a crown ether monomer and an amino monomer in an o-dichlorobenzene solvent, adding a catalyst acetic acid aqueous solution, and uniformly dispersing to form a reaction solution; the method comprises the following steps: freezing a reaction solution through a liquid nitrogen bath, vacuumizing, filling nitrogen, carrying out a heating reaction, and carrying out post-treatment operations such as washing and drying on a reaction product, so as to obtain the crown ether covalent organic framework material BADT-DB18C6-COF. The crown ether covalent organic framework material is formed by condensation of a crown ether aldehyde monomer and an amino monomer, the crown ether monomer is 4, 4 ', 4' ', 4 '''-(6, 7, 9, 10, 17, 18, 20, 21-octahydrodibenzo [B, K] [1, 4, 7, 10, 13, 16] hexaoxacyclo octadecene-2, 3, 13, 14-tetrayl) tetrabenzaldehyde, and the crown ether monomer is 4, 4 ', 4' ', 4'''-(6, 7, 9, 10, 17, 18, 20, 21-octahydrodibenzo [B, K] [1, 4, 7, 10, 13, 16] hexaoxacyclo octadecene-2, 3, 13, 14-tetrayl) tetrabenzaldehyde. The amino monomer is 4 ', 5'-bis (4-aminophenyl)-[1, 1 ': 2', 1 ''-terphenyl]-4, 4''-diamine. The crown ether covalent organic framework material BADT-DB18C6-COF prepared by the invention is mainly used as an adsorbent, is used for adsorbing and recovering uranium, thorium and americium ions from a solution, shows good adsorption capacity on radionuclides U-238, Th-232 and Am-243, and is particularly suitable for the field of spent fuel post-treatment in the nuclear industry.

The invention discloses a method and a system for rapidly measuring the concentration of radioactive radon in air in a gas flow mode based on scintillation. According to the method, the net counting rate of alpha particles is measured based on a scintillation method, and the net counting rate of the alpha particles in a corresponding time period needs to be obtained during measurement; in combination with a radon and daughter decay rule and a chamber ventilation condition, establishing a relationship between the net count of alpha particles generated by radon and daughter decay in newly sucked air in a corresponding measurement time period in the measurement chamber and the volume, the pump speed and the original air radioactivity concentration in the chamber; and a corresponding sensitivity coefficient for measuring the radioactive radon concentration of the to-be-measured air is obtained, so that the radioactive radon concentration of the to-be-measured air is obtained in real time. According to the method, the radioactive radon concentration in the air can be rapidly measured in real time under the dynamic gas flow type condition, the measurement time can be greatly saved, the change of the radon concentration in the air can be reflected in time, workers and the public can be protected against the harm of radon radiation, safety production of the nuclear industry can be promoted, and the method has wide application prospects.

The invention discloses a trusted communication method based on an FPGA (Field Programmable Gate Array) and an SOC (System On Chip), and relates to the technical field of trusted communication, an engineer station and a control station perform identity authentication by adopting an SM2 signature algorithm, acquire an SM4 key after successful authentication, and communicate by adopting an SM4 encrypted configuration information interaction mode, and the SM4 key is dynamically determined in each session. According to the invention, trusted communication in the field of nuclear industry control is realized.

The invention discloses a multi-component composite oxide dispersion strengthening molybdenum alloy and a preparation method thereof, and relates to the technical field of refractory metal powder metallurgy preparation. The molybdenum alloy comprises a molybdenum matrix and a Y-X-O composite oxide nano precipitated phase dispersed and distributed in the molybdenum matrix. The molybdenum alloy comprises the following components in percentage by mass: 1%-2% of Y2O3, 0.3%-1.2% of an active element X, 96.5%-98.7% of molybdenum and inevitable impurities, wherein X is selected from one of Ti, Zr and Hf; the Y-X-O composite oxide nano precipitated phase and the molybdenum matrix form a coherent or semi-coherent interface, and the interface mismatch degree is less than or equal to 5%. The molybdenum alloy has excellent high-temperature strength and creep resistance, and can be applied to the high-temperature fields of nuclear industry, aerospace and the like.

The invention discloses a digital twinning analysis method and a digital twinning analysis device for a life mechanism of nuclear industry DCS (Distributed Control System) equipment, and relates to the field of digital twinning of the nuclear industry DCS equipment. The method comprises the following steps: acquiring information data of DCS electronic equipment; determining residual life prediction information according to the information data based on a residual life prediction model; the residual life prediction information is used for representing state information of the DCS electronic equipment; the residual life prediction model is determined according to a physical damage mechanism model and an electrical parameter damage model; the physical damage mechanism model is a mathematical model determined through multi-physics field coupling simulation calculation according to historical working condition environment data and based on an entity geometric model of DCS electronic equipment and a service working condition test; the electrical parameter damage model is a mathematical model obtained by performing regression analysis according to historical electrical parameter data. According to the method, the service life prediction analysis of the nuclear industry DCS equipment can be quickly and accurately realized.

The invention belongs to the technical field of coatings, and particularly relates to an irradiation-resistant fireproof coating and a preparation method thereof. The radiation-resistant fireproof coating comprises a component A and a component B. The component A comprises, by weight, 15-35 parts of organosilicon modified epoxy resin, 5-10 parts of an active diluent, 20-50 parts of a dehydration char-forming catalyst, 3-10 parts of a foaming agent, 5-10 parts of a flame retardant, 0.1-0.5 part of expanded graphite, 5-10 parts of refractory fibers and 3-15 parts of a radiation-resistant filler. The radiation-resistant filler comprises silane coupling agent modified nano barium sulfate and micron boron carbide; and the component B is an amine curing agent. According to the radiation-resistant fireproof coating and the preparation method thereof, by adopting the specific silane coupling agent modified micro-nano radiation-resistant filler, the radiation-proof performance uniformity and the fire resistance after radiation resistance of the coating are effectively improved, and the radiation-resistant fireproof coating can be widely applied to nuclear power plants and various nuclear industry facilities.

The invention discloses a temperature control method for low-temperature high-NOx-concentration flue gas denitration in the nuclear industry, and relates to the technical field of flue gas denitration control. According to the method, flue gas temperature time sequence distribution, NOx concentration gradient and environment radiation intensity data are integrated through a space-time alignment algorithm, a synchronous data matrix representing a system coupling state is generated, then a temperature and efficiency response curved surface is established, a high-efficiency temperature area and an inactivation risk area are dynamically divided through fuzzy logic control, and an optimal temperature regulation and control threshold value is recognized. The drift effect of quantitative radiation on the surface temperature of the catalyst is analyzed through regression, a quantitative relation model of radiation dose and temperature zone deviation is established, and real-time correction of anti-radiation compensation parameters is achieved. And finally, optimizing the multi-objective cost function by adopting a non-dominated sorting genetic algorithm, and obtaining dynamic balance between the maximum NOx conversion rate and the minimum temperature fluctuation. And multi-parameter coupling control of a temperature field and a radiation field is realized, and the denitration efficiency stability under a low-temperature condition is remarkably improved.

The invention discloses a fine-grain tungsten-nickel-iron composite material and a low-temperature sintering preparation method thereof. The composite material takes W as a hard phase, Ni and Fe as binding phases, Y2O3 as a particle reinforcement phase and a grain growth inhibitor, and Sn as an alloy element and a sintering fluxing agent. The preparation method comprises the following steps: 1, carrying out carbon heat and hydrogen reduction on WO3, NiO, Fe2O3 and nano carbon black to obtain composite powder; 2, carrying out wet grinding with Sn and Y2O3 powder, and drying; 3, compression molding; 4, degreasing and pre-sintering treatment; and 5, low-temperature liquid-phase sintering. According to the composite material, low-temperature liquid-phase sintering is achieved by introducing the Sn element and the Y2O3, the wettability and the interface bonding force between W crystal grains and a bonding phase are improved, and the composite material with uniform components and refined crystal grains is obtained; the preparation method improves the tensile strength, microhardness and room temperature plasticity of the composite material, and is suitable for the fields of aerospace, national defense and military industry, nuclear industry, electronic information, metallurgy and the like.

The present invention belongs to the field of nuclear industry, and discloses a system and method for crushing and dissolving a quartz target tube, including a cleaning device, a drying device, a crushing device and a dissolving device. The cleaning device cleans the quartz target tube, the drying device dries the quartz target tube, the crushing device crushes the quartz target tube, and causes the crushed quartz target tube and the target material therein to fall down. The dissolving device receives the fallen quartz target tube and the target material, and dissolves the quartz target tube and the target material. The present invention cleans the quartz target tube by a cleaning device, dries the quartz target tube by a drying device, crushes the quartz target tube by a crushing device, and dissolves the quartz target tube debris and the target material by a dissolving device, which is convenient for subsequent extraction, storage and use, and has the advantages of safety, high efficiency, less impurities and high product quality.

The invention discloses an automatic barrel inner wall roughness measuring system and method based on a spectral confocal technology, relates to the technical field of measuring equipment, and solves the problems that a contact type detection method is limited in operation space and possibly damages the surface due to contact between a contact pin and an inner wall, and a visual detection method is limited in imaging effect under a complex light condition and is not high in accuracy. And quantitative characterization of roughness parameters is difficult. In the measuring process, the carrier stably moves in the axial direction of the barrel, and it is ensured that the light spot array covers the whole inner wall surface. The spectrum confocal detection module receives diffuse reflection light on the surface of the inner wall and performs roughness detection on the diffuse reflection light; and the data acquisition and processing module extracts roughness parameters in real time and generates a roughness distribution diagram. The device has the advantages of high precision, high efficiency, strong environmental adaptability, high automation degree and the like, can be widely applied to barrel inner wall roughness detection in weapon equipment manufacturing and maintenance, and is also suitable for complex pipeline inner wall roughness detection in the fields of aerospace, nuclear industry and the like.

Provided in the present invention are a preparation method for a crown ether covalent organic framework material, and the use thereof in iodine adsorption. In the present invention, an 18-crown-6-ether group is introduced into the structure of a covalent organic framework (COF) material for iodine adsorption work. The covalent organic framework material can form a one-dimensional pore channel structure in order, and the 18-crown-6-ether can be selectively complexed with iodine molecules, thereby achieving the purpose of efficient iodine adsorption. The material can perform specific iodine adsorption from high-temperature iodine steam, and the iodine steam adsorption capacity of the COF material is as high as 5.56 g / g. The COF material has a high adsorption capacity, is easy to prepare and simple to operate, has a high adsorption efficiency, and is particularly suitable for adsorbing and separating radioactive iodine in the nuclear industry.

The invention relates to the technical field of nuclear industry, in particular to a multi-tool universal coupling system for radioactive package processing and a carrying method, and the multi-tool universal coupling system for radioactive package processing comprises a main clamping piece which comprises a claw disc and clamping fingers arranged on the claw disc; the auxiliary clamping piece comprises clamps which are used for carrying different goods or executing specific operation, and interfaces which are arranged on the clamps and are in coupling fit with the clamping fingers; when the main clamping piece cannot complete specific operation, the matched clamp is selected, the clamping fingers are in coupling connection with the connector, the specific operation is executed through the clamp, the barrel container can be safely hoisted through the design of the main clamping piece and then released through the control part, and in addition, other specific carrying operation is achieved through connection of the main clamping piece and the auxiliary clamping piece. And the time for replacing the clamp is shortened.

The utility model discloses an anti-radiation high and low temperature vacuum motor, and particularly relates to the field of high and low temperature vacuum motors, the anti-radiation high and low temperature vacuum motor comprises a high and low temperature vacuum motor shell, a stator, a rotor and a rotating shaft, the stator is installed on the side wall of the inner cavity of the high and low temperature vacuum motor shell, and the rotating shaft is transversely arranged at the center of the inner cavity of the high and low temperature vacuum motor shell. A rotor is arranged on the outer diameter surface of the rotating shaft, a bearing is arranged on the contact face of the rotating shaft and the high-low temperature vacuum motor shell, and a sealing assembly is arranged on one side of the bearing. A high-low temperature vacuum motor is generally applied to fields with extremely strict environmental requirements, such as space flight and aviation and nuclear industry. Through the radiation-resistant ceramic layer, the lead-boron polyethylene plate, the nickel-based alloy layer and the modified phenolic aldehyde amine epoxy anticorrosive coating in the radiation-resistant layer in the high-low temperature vacuum motor shell, the effects of preventing the internal structure of the motor from being damaged and preventing the performance from being reduced and even losing efficacy are achieved, and through the structure, high-energy particles and radiation are prevented from penetrating through the motor shell to damage the interior of the motor. And the effect of preventing radiation is effectively achieved.

The present invention provides a three-dimensional visualization intelligent management and control system for a production line, including a data storage service module, an application service module, a graphics service module, a 3D management module, and an operation module. The operation module is used to collect material data, process data, and operation data in real time. The application service module is used to perform various business processes of the production line and obtain business application data. The graphics service module is used to generate a three-dimensional picture and a three-dimensional model and their display position. The 3D management module is used to combine material data, process data, operation data, business application data, a three-dimensional model and its display position, and a three-dimensional picture to obtain a three-dimensional monitoring interactive interface. A nuclear industry production system is also provided. The intelligent management and control system can fully display the actual status of the equipment on site, the operation process, the warehousing process, etc. to the monitoring personnel, thereby improving production efficiency and management and control safety.

The invention discloses an underwater operation nuclear industry robot which comprises an amphibious moving system, and the amphibious moving system comprises a chassis, a land moving module, an underwater moving module and an adsorption fixing module; the two sets of operation systems are installed on the front side of the top face of the chassis, each operation system comprises a multi-degree-of-freedom mechanical arm and a grabbing mechanical arm, the multi-degree-of-freedom mechanical arms are installed on the top face of the chassis, and the grabbing mechanical arms are installed at the ends of the multi-degree-of-freedom mechanical arms; the recovery and storage system is mounted on the top surface of the chassis; the visual recognition system is installed on the rear side of the top face of the chassis, and the visual recognition system comprises a supporting module, a lighting module and a recognition module; and the amphibious moving system, the operation system, the recovery and storage system and the visual identification system are all connected with the terminal controller. The underwater robot can flexibly enter an underwater operation area from the land, and is suitable for operation in various complex environments.

The invention discloses a cable channel generation method and device and a cable channel display method and system, and relates to the technical field of nuclear industry. The cable channel generation method comprises the following steps: acquiring a target model and a target cable information list; associating the N groups of target cable data information with a target model; determining P groups of target cable characteristic information in one-to-one correspondence with the P groups of target cable data information for the P groups of target cable data information contained in the target cable path channel; and generating a target cable channel according to the P groups of target cable data information and the P groups of target cable characteristic information. According to the embodiment of the invention, the method can achieve the real-time updating of the cable channel according to the upstream input change, can reduce the redundant work in the design, can reduce the human input, and can improve the design quality of a construction drawing through the development of the subsequent bridge design based on the cable channel, thereby reducing the no-load condition of a site bridge.

The invention belongs to the technical field of nuclear power, and particularly relates to a nuclear industry uranium mine mining equipment inspection management system. According to the nuclear industry uranium mine mining equipment inspection management system provided by the invention, the inspection point configuration model taking the equipment assets as the core is constructed, and deep binding of the inspection task and the equipment ledger is realized. On the basis, the system can automatically generate a matched inspection plan according to key parameters such as the operation cycle and the inspection frequency of the equipment, and accurate compilation and standardized configuration of tasks are achieved. The generation of the inspection plan does not depend on artificial experience any more, artificial omissions and configuration errors are effectively reduced, the systematicness and normalization of task coverage are improved, timely inspection and high-frequency management and control of high-risk equipment are guaranteed, and the rigid requirement of the nuclear industry for high-reliability operation and maintenance management is met.

The invention belongs to the technical field of machine vision automatic identification, and particularly relates to a radioactive article automatic identification method based on machine vision, and the method comprises the steps: labels on radioactive articles are automatically identified and clamped, and the labels are square labels with the same size, different from the background color and different in color; according to the method, the radioactive article is measured, the radiation data of the radioactive article is measured, and the radiation field is reconstructed according to the radiation data, so that the problems that working personnel are affected and the measured and acquired data are insufficient when the space dose rate in the retired environment is acquired are solved. According to the radioactive substance clamping and measuring device, the complexity and danger of radioactive substance processing in the nuclear industry are dealt with, clamping and measuring of radioactive substances are carried out through the mechanical arm, the clamping accuracy is improved, the working efficiency is greatly improved, and the safety of workers is guaranteed.

The wallboard module of the steel plate concrete wall comprises wallboards, tie bars and sleeves, each wallboard comprises a first area and a second area, each second area is an area where a through-wall pipeline needs to penetrate through the corresponding wallboard, each tie bar is located between the two opposite wallboards, the two ends of each tie bar are connected to tie positions in the corresponding first area, and each tie bar is located in the corresponding sleeve. The sleeve is of a tubular structure meeting a set relation with the equivalent strength of the section of the tie bar, the sleeve is located between the two oppositely-arranged wallboards, the two ends of the sleeve are connected to the tie positions in the second area respectively, and an inner hole of the sleeve serves as a channel for the wall penetrating pipeline to penetrate through the wallboards. The wallboard module of the steel plate concrete wall is simple in structure and reasonable in layout, a path can be provided for a through-wall pipeline, meanwhile, the original structural balance is not damaged, the construction flexibility is improved, the construction difficulty is reduced, and the economical efficiency is improved. The invention further provides a nuclear industry factory building, a concrete unit manufacturing method and a nuclear industry factory building manufacturing method.

The invention provides a graphene-loaded metal organic framework composite material as well as a preparation method and application thereof. The graphene-loaded metal organic framework composite material comprises a zirconium-organic framework material and a graphene active component, wherein an organic ligand of the zirconium-organic framework material is ellagic acid. The graphene-loaded metal organic framework composite material disclosed by the invention has an excellent adsorption effect on high-valence metal ions, so that the composite material has application potential in the aspect of adsorbing and removing radionuclides in the field of nuclear industry.

The invention discloses a multifunctional variable-diameter nuclear waste conveying pipeline cleaning robot, and relates to the technical field of nuclear industry pipeline maintenance equipment.The multifunctional variable-diameter nuclear waste conveying pipeline cleaning robot comprises a walking module, a variable-diameter module, a cleaning module and a detection module, and all the modules are integrated on a machine body frame; a collaborative linkage design of a series elastic driver (a main driving end) and a bionic joint leg (a driven wheel end) is adopted as the core, the main driving end adapts to nuclear pipeline advancing impact through elastic buffering, and the driven wheel end adapts to a complex inner wall through flexible posture adjustment. The variable-diameter module is linked with a connecting rod to adjust the radius of the wheel set to realize pipe diameter self-adaption; the cleaning module integrates a rotating brush and a cavitation jet device to remove radioactive scales; the detection module carries a sensor and a camera to monitor the pipeline state. The robot can complete cleaning and monitoring of nuclear pipelines of multiple specifications, and stable and smooth operation of the robot in pipelines of different pipe diameters is guaranteed through linkage of the series elastic drivers and the bionic joint legs.

The invention discloses a unit area heat release rate determination method and a related method and related equipment thereof, and relates to the technical field of nuclear industry. The unit area heat release rate determination method is used for a target solvent and comprises the steps that the initial unit area heat release rate of the target solvent in an initial state, the initial combustion duration of the target solvent in the initial state and the target combustion duration of the target solvent in a target state are obtained, and the target solvent is in an inverted cone shape in the combustion process; and determining a target unit area heat release rate of the target solvent in the target state according to the initial unit area heat release rate, the initial combustion duration and the target combustion duration. According to the embodiment of the invention, the method fully considers the influence of the initial combustion duration and the target combustion duration on the heat release rate of the target unit area, so that the accuracy of determining the heat release rate of the target unit area can be improved.

The invention discloses a preparation method of an ultra-smooth nanocrystalline tungsten coating on the surface of an emitter, the tungsten coating is prepared by adopting a magnetron sputtering method, and the specific process is as follows: pretreating an emitter workpiece, then placing the emitter workpiece in a vacuum chamber, pre-vacuumizing, then introducing inert gas, cleaning the surface of the emitter workpiece by utilizing gas ion reverse sputtering, and finally removing the surface of the emitter workpiece. And then adjusting the gas pressure, bombarding and cleaning the surface of the emitter workpiece by using metal ions, and finally sputtering and depositing to form the tungsten coating. The tungsten coating is prepared through the magnetron sputtering technology, the tungsten coating has the characteristics of being compact in structure, good in combination and uniform and smooth in surface, the mechanical property and structural stability of the tungsten coating in the high-temperature service environment can be guaranteed, the deposition technology is simple, the preparation efficiency is high, and the tungsten coating is green and free of pollution, in addition, preparation of the tungsten coating composed of different phases can be achieved, and the application prospect is wide. The application requirements in the fields of electronic industry, nuclear industry and the like are met.

The invention discloses a nano precipitated phase reinforced refractory high-entropy alloy and a preparation method thereof, and relates to the technical field of preparation of novel metal materials. According to the method, the NbMoTaW refractory high-entropy alloy serves as a base material, the phase separation phenomenon of the base is effectively induced by introducing a high-proportion Zr element into the base, and the formation of a nanoscale precipitated phase which is evenly and dispersively distributed is successfully achieved by combining specific solid solution and aging treatment processes. The refractory high-entropy alloy prepared through the method shows excellent performance characteristics, the basic properties of the material are remarkably improved, more possibilities are provided for application of the refractory high-entropy alloy in an extreme environment, and the refractory high-entropy alloy is expected to be widely applied and developed in the fields of aerospace, nuclear industry and the like.

The invention relates to the technical field of manufacturing of proximity switches for the nuclear industry, in particular to a sealed passive proximity switch with a permanent magnetic mechanism, which comprises a shell, an execution mechanism, a first fastening nut, a sealed base and a cable outgoing line, and is characterized in that the upper end of the execution mechanism is connected with the bottom of the shell, and the lower end of the execution mechanism is connected with the fastening nut in a matched manner; the bottom of the fastening nut is connected with the sealing base in a matched mode, and the cable outgoing line is arranged at the bottom of the sealing base. Compared with the prior art, the contact system has the beneficial effects that the contact system not only has the characteristics of accurate induction action of an external magnetic object, high stability of the contact system and high sealing protection grade, but also has long-term contact stability under a severe environment condition, and realizes long-term reliable work of the whole machine.

The sealing swing hydraulic joint comprises a joint sleeve, a fork frame, a rotary hydraulic cylinder, a sealing assembly and a wire passing hole, the joint sleeve is connected with a driving arm pipe, a cavity is formed in the joint sleeve, and the sealing assembly can seal and block an opening of the cavity in a movable and rotary mode in the axial direction of the cavity so that the sealing assembly and the joint sleeve can form a sealing cavity wrapping the rotary hydraulic cylinder. The rotary hydraulic cylinder is contained in the sealing cavity, a cylinder body and a driving end are fixedly connected with the joint sleeve and the sealing assembly respectively, the fork frame is connected with the driven arm pipe and fixedly connected with the sealing assembly, the sealing assembly serves as the hinged position of the fork frame and the joint sleeve, and under driving of the rotary hydraulic cylinder, the driven arm pipe is driven to swing relative to the driving arm pipe. The wire passing hole is an internal continuous hole formed in the joint sleeve, the sealing assembly and the fork frame so that the pipe cable can penetrate from the driving arm pipe to the driven arm pipe in a sealed mode. The joint is reasonable and ingenious in structural layout, excellent in sealing performance and easy to decontaminate and maintain. The invention further provides operation equipment for the nuclear industry.

The invention provides a teleoperation radiation-resistant metal mechanical property test sample preparation system, and belongs to the technical field of nuclear industry science, the teleoperation radiation-resistant metal mechanical property test sample preparation system comprises a cutting machine body for preparing and processing all radioactive metal samples, and the preparation system further comprises a purification system installed on the right side of the cutting machine body; the shielding system is mounted on the cutting machine body and the purification system; the cooling system is mounted on the rear side of the purification system; the automatic threading device is mounted on the cutting machine body and is used for providing uninterrupted copper wires for the sample preparation process; and the remote control system is installed at the far end and used for driving the cutting machine body, the purification system, the cooling system and the automatic wire penetrating device and monitoring the operation states of all the systems at the same time. According to the invention, the contradiction between irradiation sample preparation and harm of radioactivity to people and equipment is effectively solved, a radioactive source and an operator as well as the radioactive source and the sample preparation equipment can be isolated, and the operator and the sample preparation equipment are protected from being damaged by radiation.

The invention discloses a nuclear power plant fuel operation accident source item result determination method and device and a nuclear power plant fuel operation accident alarm method and system, and relates to the technical field of nuclear industry. The method for determining the fuel operation accident source item result of the nuclear power plant comprises the following steps: acquiring a target decontamination factor corresponding to a target nuclide in a first time period and the total concentration of aerosol iodine retained in a spent pool of the nuclear power plant in a second time period; determining a first release amount corresponding to the target nuclide in the first time period according to the target decontamination factor; according to the total concentration of iodine in the aerosol, determining the share of iodine volatilized in the form of elements in the spent fuel pool in the second time period; determining a second release amount of the element iodine in a second time period according to the iodine share; and generating a fuel operation accident source item result of the nuclear power plant according to the first release amount and the second release amount. According to the embodiment of the invention, the method can improve the accuracy of determining the fuel operation accident source item result of the nuclear power plant.