146 results about "Nuclear facilities" patented technology

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 discloses a parameter optimization method and system based on an agent model and multi-algorithm gradient collaboration, and relates to the technical field of nuclear engineering and nuclear security, and the method comprises the steps: firstly determining a nuclear facility parameter combination, carrying out the high-fidelity calculation through a Monte Carlo program to obtain a Keff value, and constructing a training set; training a micro-proxy model capable of predicting a Keff value and gradient information through a feedforward neural network in combination with a back propagation algorithm, taking the micro-proxy model as a target function, taking the minimum absolute error of a Keff predicted value and a target value as an optimization target, and generating candidate parameter solutions through global exploration of a hybrid optimization algorithm; and an optimal parameter combination candidate solution is obtained through gradient-assisted local optimization, and finally, through Monte Carlo program verification, if the error reaches the standard, the optimal parameter combination candidate solution is used as a final parameter combination solution. The problem that a parameter optimization method in the prior art cannot give consideration to calculation efficiency and precision is solved.

The invention belongs to the technical field of robot teleoperation and haptic interaction, and provides a multi-mode force feedback control method and system for nuclear facility robot operation, and the method comprises the steps: collecting the state information of a master arm and a slave arm in real time, and dynamically scheduling a haptic calculation strategy according to a task state; a fast estimation strategy is enabled in the fast transit mode. Further, real environment interaction force is obtained based on dynamic model compensation and net interaction force extraction; combining the dynamically selected multi-mode force feedback parameters, and synthesizing and outputting a touch instruction to the main arm. Meanwhile, admittance correction and feed-forward compensation are carried out on a slave arm motion instruction through net interaction force and dynamic internal force, synchronous output is carried out after safety optimization, and the slave arm is controlled to move. The problems of poor task adaptability, force sense distortion and insufficient safety in nuclear facility teleoperation are solved, and intelligent, high-fidelity and safe robot teleoperation is achieved.

The invention discloses a preparation method of a starch-based gel color developing material for visual detection of airborne iodine nuclides, which comprises the following steps: adding starch, a polymer matrix material and a plasticizer into deionized water for soaking and uniformly stirring to obtain a starch-based gel matrix solution; placing the starch-based gel matrix solution at a certain temperature, and stirring to obtain gel paste; and injecting the gel paste liquid into a mold, and carrying out freeze-thaw cycle to obtain the starch-based gel color developing material for airborne iodine nuclide visual detection. The starch-based gel color developing material has the characteristics of quick response, stable color development and lasting color and luster for airborne iodine nuclide at normal temperature, has excellent mechanical strength, machinability and recycling performance, can be flexibly processed into forms such as a film and a test piece, or can be integrated in various detection devices, and has a wide application prospect. The method is suitable for places needing airborne iodine nuclide detection, such as nuclear medicine laboratories, nuclear facilities / nuclear equipment and the like, and meets the requirements of real-time visual detection and early warning.

The invention relates to the technical field of nuclear facility pipeline heating. The invention provides a pipeline heating device and an in-reactor test facility. The pipeline heating device comprises a magnetic conduction layer, a heat conduction layer, a heat preservation layer and an electromagnetic induction coil, the magnetic conduction layer is made of a magnetic alloy material, and the magnetic conduction layer is enclosed and internally forms a heating area used for containing a pipeline; the heat conduction layer is located on the side, facing the heating area, of the magnetic conduction layer and used for transmitting heat of the magnetic conduction layer to the pipeline. The heat preservation layer wraps the side, away from the heating area, of the magnetic conduction layer. The electromagnetic induction coil is wound around the side, away from the heating area, of the heat preservation layer. The magnetic conductive layer made of the magnetic alloy material serves as a main absorption and conversion carrier of magnetic field energy, the eddy current effect can be remarkably enhanced, the problem that the heating efficiency is insufficient due to low magnetic conductivity of the austenitic stainless steel pipeline is solved, and the heating efficiency is greatly improved. The arrangement of the magnetic conductive layer can fundamentally avoid material microscopic damage caused by direct action of a magnetic field, and the safety is higher.

A nuclear installation comprising at least one modular nuclear reactor (SMR) and a reactor vessel well delimiting a water basin in which the SMR reactor unit is immersed. The invention relates to a nuclear installation comprising: at least one SMR reactor unit (4) for heat generation, delimited by a reactor vessel (40, 41, 42); a reactor vessel well (100) delimiting a water-filled basin (B) forming part of a secondary circuit, in which the reactor vessel is immersed; at least one heat exchanger (49) between the primary circuit of the SMR reactor and the secondary circuit, arranged outside the reactor vessel and in the water basin. Figure for the abstract: Fig. 6

The invention relates to the technical field of neutron measurement, and particularly discloses a multi-activation foil and method for measuring a neutron energy spectrum. The multi-activation foil comprises a shell and an activation sheet placed in the shell, and the activation sheet sequentially comprises Ni, Sc, Au, W, Cu, Pt, In, Zn and Fe from top to bottom. The activated foil can realize high-resolution measurement of a neutron spectrum in a very small space, has the characteristics of size miniaturization, wide energy response range, wide neutron fluence rate application range, controllable manufacturing tolerance, optimized material ratio and the like, and is suitable for neutron spectrum and neutron dose measurement of a small-scale region of a nuclear facility and neutron dose measurement of a small-scale region of a nuclear facility. The method can also be popularized and applied to fine dose field distribution measurement of a large-scale area of a nuclear facility, and provides accurate data support for safe operation, shielding verification and radiation protection of the nuclear facility.

The invention discloses a liquid-phase deuterium-doped anti-radiation optical fiber, a preparation method and application, and belongs to the technical field of manufacturing of anti-radiation optical fibers. According to the method, deuterium is stably doped into a fiber core in the form of OD groups in the preparation stage of the optical fiber preform through an improved chemical vapor deposition combined solution doping technology, so that the problems that gas is easy to leak and the radiation resistance is attenuated along with time in a traditional gas loading technology are solved. The preparation process comprises the steps of pretreatment of the deposition tube, preparation of the barrier layer and the porous loose layer, solution soaking OD group doping, sintering collapse and wire drawing treatment. An OD group can be detected in the prepared optical fiber, the radiation resistance of the optical fiber is remarkably improved, after the optical fiber is irradiated by gamma rays with the total dose of 200Gy (Si), the radiation-induced attenuation is remarkably lower than that of a common optical fiber without the OD group, and a material basis is provided for long-term reliable application of the optical fiber in radiation environments such as space exploration and nuclear facilities.

The invention belongs to the technical field of nuclear facility decommissioning and three-waste treatment, and particularly relates to an automatic laser decontamination system and method for polluted metal waste of a nuclear power plant. The decontamination / cutting workbench is transferred to all stations and an operation table through a transfer trolley; the operation table is used for controlling the transfer of the transfer trolley, controlling the operation of the workpiece turnover device, measuring the size of a to-be-decontaminated item and measuring the surface contamination level and radiation level of the to-be-decontaminated item before and after decontaminating; and the controller is used for recording a measurement result, presetting cutting parameters and decontamination process parameters of a to-be-decontaminated item, and controlling the laser cutting device, the laser cleaning device and the laser stripping device to carry out laser cutting and automatic laser decontamination operation. According to the invention, the labor intensity of personnel can be effectively reduced, the exposure dose of the personnel is reduced, the decontamination working efficiency is improved, waste degradation or clean control of surface polluted metal waste is realized, and waste minimization is further realized.

The objective is to provide a method for dissolving solids that is excellent at dissolving solids generated in nuclear facilities. [Solution] A method for dissolving a solid generated at a nuclear facility, comprising dissolving the solid in a solution containing at least one of carbonate ions and bicarbonate ions, and at least one of potassium ions and cesium ions.

The invention relates to the technical field of neutron measurement, and particularly discloses a thermoluminescence field dosimeter for measuring neutron energy spectrum.The thermoluminescence field dosimeter comprises a thermoluminescence field dosimeter body, and the thermoluminescence field dosimeter body comprises a front-end assembly, a rear-end assembly and a center assembly located between the front-end assembly and the rear-end assembly; the center assembly and the rear end assembly are detachably connected with the front end assembly. Wherein the distance between the front surface of the central assembly and the front surface of the front end assembly is 1mm, the distance between the front surface of the rear end assembly and the front surface of the front end assembly is 7mm, and the front surface of the central assembly and the front surface of the rear end assembly are respectively provided with a 6LiF thermoluminescence dosage piece and a 7LiF thermoluminescence dosage piece. The thermoluminescence field dosimeter is wide in neutron energy response range, covers 0.0253 eV-20 MeV, can be suitable for neutron energy spectrum measurement of nuclear facilities such as fission reactors, fusion reactors and medical accelerators, and is particularly suitable for measurement in measurement occasions with narrow spaces and large neutron field gradients.

The application provides an automatic sampling and measuring device for radioactive aerosol and gaseous tritium in radioactive gaseous effluent. The measuring device comprises a radioactive aerosol measuring module and a gaseous tritium measuring module integrated in the measuring device, and the radioactive aerosol measuring module and the gaseous tritium measuring module are communicated with a gaseous effluent pipeline through sampling pipelines. The measuring device of the application can greatly save labor, realize unattended and long-time online monitoring, flexibly adjust the sampling and monitoring frequency, and improve the monitoring efficiency. In addition, in the case of a nuclear accident, the emergency monitoring mode can be quickly started to quickly respond to the accident monitoring requirements, so as to realize continuous, online and automatic monitoring of the concentration of radioactive aerosol and gaseous tritium in the effluent of a nuclear facility.

Embodiments of the present application provide a method and system for three-dimensional waste cutting and packing simulation for nuclear facility decommissioning engineering. The method comprises obtaining three-dimensional model data, waste storage container data and cutting constraint data of a target nuclear facility; performing format conversion on the three-dimensional model data and the waste storage container data to generate target three-dimensional data and target container data; performing cutting and packing simulation based on a preset optimization engine, the target three-dimensional data, the target container data and the cutting constraint data to generate a simulation scheme; optimizing the simulation scheme based on a preset optimization parameter to generate a Pareto frontier solution set; determining a final selection result in response to user selection in the Pareto frontier solution set; and generating a cutting and packing simulation engineering report based on the final selection result. In this way, waste can be efficiently processed flexibly.

Safety container cooling system (10) comprising a sealed safety container (12) of a nuclear facility, - with a heat exchanger for heat transfer between a medium to be cooled and a cooling medium, - with first means to extract the medium to be cooled from the safety vessel (12) in a first cooling circuit and supply it to the heat exchanger and, after it has flowed through the heat exchanger, return it to the safety vessel (12), wherein the first means comprise a first pumping device (38) to pump the medium, now cooled by the heat exchanger, back into the safety vessel (12), - with second means to supply the recoolant from a coolant reservoir to the heat exchanger and to return it to the coolant reservoir after it has passed through the heat exchanger, wherein the second means comprise a second pumping device located outside the safety vessel (12) to set the recoolant in motion, wherein the second means comprise a turbine (40) which is driven by the flow of the cooling medium, wherein the first pump device (38) is coupled to the turbine (40) in such a way that it is driven by it, characterized by the fact that the first pumping device (38) and the turbine (40) are arranged outside the safety container (12), that the heat exchanger is a condenser (30) arranged outside the safety container (12), that the first means have a withdrawal device (24) in the safety container (12) for withdrawing the medium to be cooled from the safety container (12), which has a steam component and an air component, and at least the steam component is directed to the condenser (30), that the steam component is condensed to water by the condenser (30), that the water is pumped back into the safety container (12) as a cooled medium by the first pumping device (38).

The present application relates to the technical field of nuclear power plant ventilation purification, and discloses an equivalent test bench for evaluating the performance of iodine removal and a verification method, the verification method comprising: obtaining three carbon samples with different iodine removal efficiencies; based on the three carbon samples, performing a first test under the French standard system, a second test under the American standard system, a third test under different humidity conditions, and a fourth test under accident conditions on the same test bench, and recording the corresponding test results; comprehensively analyzing the test results corresponding to the four tests to obtain the test equivalent relationship between the French standard system and the American standard system, the numerical relationship between humidity and iodine removal efficiency, and the change rule of iodine removal efficiency after accident radiation. The present application accurately establishes the quantitative relationship between the French standard and the American standard, humidity and iodine removal efficiency, and accident radiation and performance decay based on a unified test bench; provides a unified scientific basis for the performance evaluation of iodine adsorbers in nuclear power plants, and improves the safety and reliability of gaseous radioactive contamination protection of nuclear facilities.

A hybrid power generation system which includes a nuclear facility comprising a nuclear reactor and an exclusion zone. A thermal energy storage, a nuclear steam supply system located, and a solar energy collection system are all located within the exclusion zone. The thermal energy storage vessel contains a thermal mass composition operable to store thermal energy. The nuclear steam supply system has a nuclear reactor and a working fluid loop. The working fluid loop is configured to circulate a working fluid from a steam generator through the thermal energy storage vessel to absorb thermal energy and heat the working fluid for introduction to an electricity generating system. The solar energy collection system includes a heat transfer loop heated via a solar collector. The heat transfer loop is configured to circulate a heated heat transfer fluid to add thermal energy to the thermal mass composition in the thermal energy storage vessel.

The invention relates to the technical field of nuclear facility installation, and discloses a modular self-locking anti-vibration clamping rail connecting system for nuclear facilities, which solves the problems of long construction period, large field operation quantity, difficulty in quality control, large limitation of field conditions and the like due to the fact that most of the existing nuclear facilities adopt a traditional integral construction mode, and comprises two rails, supporting strips are fixedly installed between the two ends of the bottoms of the two rails, silicone rubber pads are fixedly installed at the two ends of the bottoms of the two supporting strips, three high-damping rubber supporting columns are fixedly installed at the bottoms of the two rails correspondingly, and the middles of the surfaces of the two rails are sleeved with two sliding tables correspondingly. Limiting blocks are fixedly mounted on the inner walls of the two sides of the four sliding tables correspondingly, and limiting grooves are formed in the two sides of the two rails correspondingly; according to the clamping rail connecting system, a single nuclear facility is installed in a modularized mode to replace a traditional overall construction mode, so that efficient installation and flexible adjustment are achieved, and the modern construction requirement is met.

The invention belongs to the technical field of nuclear facility decommissioning, and particularly discloses an underwater laser cleaning and cutting combined machining device and a using method, cleaning and cutting are achieved through refraction and reflection of cleaning laser by scanning an X / Y-axis galvanometer set and a dichroscope and transmission of cutting laser by the dichroscope, and coaxial focusing is achieved through a common field lens; a gas-liquid coaxial composite nozzle is arranged at the bottom, and center auxiliary airflow and annular high-pressure laminar flow water can be independently regulated and controlled; millisecond-level process switching is matched, and instant cutting is carried out after cleaning is completed at the same underwater station. Aiming at the problems of low efficiency, high safety risk, more secondary pollution, poor cutting quality and the like in the decontamination and disintegration process of the high-level metal part of the nuclear power station, the invention does not generate radioactive waste liquid, effectively avoids secondary pollution, remarkably improves the cutting quality, the operation safety and the system reliability, and is suitable for green and efficient retirement operation in a high-radioactivity environment.

The application discloses a glove box decommissioning robot, a glove box decommissioning system and a decommissioning method of a nuclear facility, which enables the mechanical arm of a crawler robot to accurately enter a glove operation hole and clean and decontaminate the inside of the glove box. The glove box decommissioning robot comprises a crawler walking system (1), an arm moving system (3), a mechanical arm system (2) and an electric control system (7). The arm moving system (3) comprises a horizontal screw module and a vertical screw module. The horizontal screw module is fixed at the front end of the crawler walking system (1) and is used for linear motion in the horizontal direction. The vertical screw module is fixed on the sliding block of the horizontal screw module and is used for linear motion in the vertical direction. The mechanical arm system (2) comprises two mechanical arms, and the two mechanical arms are fixed on the sliding blocks of the vertical screw module and are moved under the drive of the arm moving system (3). The roots of the two mechanical arms rotate around the same axis.

The invention belongs to the technical field of nuclear energy accident treatment, and relates to a high-temperature gas cooled reactor accident condition typical nuclide chemical form research method and system and a readable medium. Inputting the data into an accident source item calculation model to obtain the content change condition of each radionuclide and impurity element along with time; obtaining a chemical form evolution result along with temperature and a chemical form evolution result along with time through a thermodynamic method; determining a Latin hypercube sampling range, constructing an EMSAC input file, and running EMSAC calculation to obtain an element chemical form database in a multi-parameter variation range; and obtaining a correlation analysis result of the element chemical form database. The method solves the problems that in the prior art, accident source items cannot be processed, chemical forms evolve along with time and dimension explosion occurs during multi-parameter multi-change range calculation, accident source item whole-process calculation is completed for the first time, and theoretical reference is provided for subsequent radiation safety evaluation of nuclear facilities.

The invention relates to the technical field of radiation monitoring, and discloses a portable aerosol monitor and a monitoring method. The monitor comprises an aerosol box body assembly, a sucking pump, a filter paper assembly, a probe assembly, an electronics control assembly and a man-machine interaction screen assembly. The filter paper replacement device is characterized in that the design of the drawable filter paper assembly is adopted, a unique locking sealing mechanism and a spring positioning ball are matched with a radial sealing ring, rapid replacement and double sealing of filter paper are achieved, and cross contamination in the replacement process is effectively avoided. Meanwhile, the equipment is integrated with a PIPS detector for alpha / beta radioactivity measurement, signal processing and energy spectrum analysis are carried out in combination with an electronic system, and the equipment has the functions of flow monitoring, sound-light alarm, positioning communication and the like. The device is compact in structure, convenient to carry and easy and convenient to operate, solves the problems that traditional equipment is large in size, filter paper is prone to being polluted, and sealing performance is poor, remarkably improves reliability and accuracy of monitoring data, and is particularly suitable for nuclear facility surrounding environment monitoring and emergency response scenes.

The invention discloses an online magnetic field measurement system and method of a linear fusion device, and relates to the technical field of magnetic field measurement of nuclear facilities. The on-line magnetic field measurement system of the linear fusion device comprises a circular track of which the circle center is aligned with the central axis of the magnetic field of the linear fusion device, the circular track is provided with a circular motion part, the circular motion part is connected with a transverse track, the transverse track is provided with a transverse motion part, and the transverse motion part is connected with a longitudinal track. The longitudinal track is provided with a longitudinal moving part which is connected with a magnetic field detector. The circular track and the circular motion piece are matched to enable the magnetic field detector to do circular motion, the transverse track and the transverse motion piece are matched to enable the magnetic field detector to do transverse motion, and the longitudinal track and the longitudinal motion piece are matched to enable the magnetic field detector to move from the outer side to the center in the direction perpendicular to the magnetic field axis of the linear fusion device. Magnetic field measurement of a single probe at any position in the space can be realized, the measurement precision is high, the operability is good, and the measurement efficiency is improved.

The application discloses a kind of point kernel integration calculation model efficient modeling method based on scene three-dimensional model, comprising: the three-dimensional modeling program is imported to nuclear facility scene three-dimensional model and the object to be modeled is split;For shielding type object, the shielding calculation model is obtained by copying on the basis of the three-dimensional model, the shielding calculation model is named, until the processing of all shielding type objects is completed;Determine the position of radioactive source term, when there is radiation field measured data, establish the quantitative mapping of dose rate and color, convert measured data into corresponding spatial position color ball-shaped measuring point to assist positioning;Source term calculation model is established by copying at the source term position and write material, nuclide and activity information;The parameters of the shielding calculation model and the source term calculation model are extracted by secondary development script and basic body information extraction algorithm;The parameters are stored according to point kernel integration calculation program input card format, and the point kernel integration calculation model for γ radiation field calculation is obtained.

The invention provides an integrated modular shielding type filtering device, and relates to the technical field of nuclear facility air purification, the device comprises: a filtering shell, the side wall of which is provided with an air inlet and an air outlet; the pre-filter assembly is arranged in the filtering shell, and the pre-filter assembly comprises a pre-filter cylinder and a pre-filter installed in the pre-filter cylinder; the high-efficiency filter assembly is arranged in the filtering shell, and the high-efficiency filter assembly comprises an HEPA filter cylinder and an HEPA filter installed in the HEPA filter cylinder; wherein the pre-filter and the HEPA filter are both of a cylindrical structure with the top end open and the side wall and the bottom closed, and the top ends of the pre-filter and the HEPA filter are both communicated with an air inlet channel formed by air inlets. By optimizing airflow organization and a sealing structure and integrating an on-line monitoring system, the industrial problem that radioactive substances escape when the filter element is replaced is fundamentally solved, and meanwhile the device has the advantages of being precise in maintenance, reliable in shielding and convenient and fast in modular layout.

A radiation source identification system using Compton image projection in a three-dimensional virtual space, according to the present invention, comprises: a gamma image generation module that includes a gamma camera and generates 4-pi full-solid-angle Compton image data; an indoor positioning module that includes a plurality of fixed beacons and one mobile beacon and generates coordinates of the mobile beacon; a rotating support module that includes a fixed plate on which the mobile beacon of the indoor positioning module and the gamma image generation module are mounted, and a driving control device that rotates the fixed plate according to an input directional angle; and an integrated data management module that stores and manages a three-dimensional building information model that depicts each facility of a nuclear facility as a three-dimensional object in a three-dimensional virtual space, converts the coordinates of the indoor positioning module and the directional angle of the rotating support module into reference coordinates and a reference direction in the three-dimensional virtual space, respectively, receives the Compton image data of the gamma image generation module, aligns same to the reference coordinates and the reference direction to project same, and identifies a radiation source.

The invention belongs to the field of nuclear facility transfer devices, and particularly relates to a rapid transfer device for radiation multi-shape samples transmitted by a pneumatic pipeline, which is arranged in a sealed pneumatic transmission pipeline formed by connecting a straight line section and a curve section, runs under the driving of compressed gas, and is characterized by comprising a sample box, the sample box is used for containing and clamping samples and comprises a shell provided with an access door, a cover plate used for sealing the access door and a flexible clamping module arranged in the shell. The front end and the rear end of the sample box shell are connected with a guide plug through a universal coupling, and the guide plug is of a streamline structure. According to the invention, the flexible clamp with the pin holes arranged in a matrix manner and the pluggable cylindrical pins is arranged, and the locking bolts are combined for fastening, so that the sample contour is accurately and adjustably matched, various samples with different sizes and shapes can be fixedly clamped, and the displacement and rolling of the samples are effectively prevented in the transfer process.

The present invention provides a blowout panel device that has the contradictory functions of rapid opening and slow stopping of the blowout panel. [Solution] The blowout panel device 100 comprises a blowout panel 1 that closes an opening 30 in the building of a nuclear-related facility, a hinge portion 2 that fixes the blowout panel to the building structure at the top or bottom, and a buffer mechanism 110 with one end connected to the structure and having a spring and damper arranged in parallel. The other end of the blowout panel 1 and the buffer mechanism 110 are attached via a flexible member (for example, a wire 7). When the door of the blowout panel 1 is opened, the door opens almost without load up to a predetermined door opening, and when it exceeds the predetermined door opening, the buffer mechanism 110 operates and the blowout panel stops at a predetermined limited door opening below the limit door opening where damage occurs, and then the blowout panel 1 returns in the direction of closing to the predetermined door opening.

A nuclear-grade radiation-resistant infrared video monitoring system belongs to the technical field of nuclear facility safety monitoring, and comprises a radiation-resistant infrared camera used for collecting infrared video data in a strong nuclear radiation environment; the image processing unit is used for performing enhancement processing on the infrared video data, removing non-uniform fixed mode noise caused by radiation and obtaining an enhanced video image; and the intelligent analysis and prediction unit is used for carrying out quantitative identification on the enhanced video image, obtaining pipeline defects in the video image and carrying out risk prediction. The problems that no available infrared monitoring equipment exists in a radiation area of an existing nuclear facility, the existing nuclear facility depends on an imported visible light camera (the problems of short service life, sensitivity to temperature, poor image quality and the like), and the existing nuclear facility lacks intelligent early warning capability are solved.

This invention belongs to the field of nuclear facility radiation monitoring technology and aims to solve the problem of low accuracy in identifying and measuring multiple radioactive particles in mixed radiation fields. It provides a quantitative measurement method for multiple radioactive particles in mixed fields. By building a high-speed waveform data acquisition system, it achieves high-speed, high-precision acquisition of radioactive particle waveform data and reconstruction of the entire waveform under different testing conditions. It also utilizes a convolutional neural network model to complete adaptive feature extraction and accurate classification of radioactive particles from the full waveform data. Simultaneously, it establishes a waveform database covering four types of radioactive particles (α, β, γ, and n) under multiple testing conditions. By combining the database with waveform feature matching, it ultimately achieves rapid, high-precision identification and accurate quantitative measurement of the four types of radioactive particles in complex environments, significantly improving the technical level and practical application effect of nuclear facility radiation monitoring.

The invention relates to the technical field of nuclear facilities, and discloses a deuterium-tritium fusion device containing zoning method, device, equipment and medium, and the method comprises the steps: preliminarily dividing each tritium-related room into a plurality of tritium-related regions with different tritium containing grades based on a preset tritium-related concentration limit value; identifying a transition room between two tritium-related areas with adjacent spatial positions and adjacent tritium containing levels, and generating a plurality of different candidate zoning schemes by adjusting the tritium-related area to which the transition room belongs; for any candidate zoning scheme, determining system balance time of the candidate zoning scheme based on the space volume of each tritium-related region, the annual average tritium release rate and the preset net exhaust air rate; and identifying the shortest system balance time in each system balance time, and determining the candidate partitioning scheme corresponding to the shortest system balance time as a target partitioning scheme. The method has the beneficial effect that the dynamic response performance of the negative pressure ventilation system is optimized.