699 results about "Nuclear radiation" patented technology

The invention discloses a nuclear radiation index early warning system based on multi-algorithm fusion, and the system comprises an environment data collection module which is used for collecting gamma-ray dose rate data, wind speed data, wind direction data and geographic position information, and constructing a nuclear radiation environment data set; the dose rate prediction module is used for predicting a future change trend of gamma ray dose rate data based on a sparse recurrent neural network model; the anomaly detection module is used for identifying an abnormal mutation point and positioning the position of a high-risk sensor; the diffusion region modeling module is used for calculating a nuclear radiation diffusion influence region; the grid risk evolution module is used for simulating time sequence evolution of a regular grid risk state based on the multi-state cellular automaton; and the fusion judgment module is used for fusing output results and generating a final early warning grade and a spatial risk distribution result. According to the invention, accurate prediction of the nuclear radiation risk and dynamic space early warning are realized, and the early warning accuracy and response efficiency are significantly improved.

The invention relates to the technical field of unmanned aerial vehicle-mounted nuclear radiation detection, and provides an unmanned aerial vehicle-mounted nuclear radiation detection method and system based on deep learning, and the method comprises the steps: collecting a gamma energy spectrum signal, and carrying out the digitization of the gamma energy spectrum signal, and obtaining original energy spectrum data; preprocessing the original energy spectrum data to obtain preprocessed energy spectrum data; constructing a nuclide identification model based on a deep learning network, and performing nuclide identification on the preprocessed energy spectrum data to obtain an original nuclide identification result; performing post-processing analysis and refinement on the original nuclide identification result to obtain a nuclide identification result; and fusing the nuclide identification result with the geographic position information to obtain a nuclear radiation pollution distribution diagram, and setting a multi-level early warning mechanism based on nuclide types and intensity. According to the invention, the precision of nuclide identification in a complex environment is improved, and high-sensitivity detection of various nuclides under the condition of low signal-to-noise ratio is realized.

The invention discloses an intelligent nuclear radiation dose real-time monitoring system based on deep learning, and the system comprises the steps: S1, a multi-mode sensing module which is used for outputting radiation intensity data with timestamps, environment image data and geographic space position information; s2, a preprocessing module used for outputting a structured feature sequence; s3, a fusion modeling module which is used for generating a unified fusion feature vector; s4, an end-edge reasoning module which is used for processing the fusion feature vector in stages and generating a nuclear radiation dose prediction result; s5, the task scheduling module is used for dynamically determining whether the reasoning task is executed on the end side or the edge node; s6, an anomaly detection module which is used for determining whether there is an abnormal change of the nuclear radiation dose; and S7, the system control module is used for coordinating the modules. The method has the advantages of being high in environmental adaptability, fast in reasoning response and high in anomaly recognition precision.

The invention relates to the technical field of intelligent evaluation and early warning methods, in particular to a nuclear radiation dose space distribution intelligent evaluation and early warning method and system, and the method comprises the following steps: obtaining multi-source monitoring data which comprises gamma radiation dose, alpha radiation dose and beta radiation dose measuring instrument data; performing fusion and enhancement processing on the multi-source monitoring data to obtain an enhanced radiation monitoring signal; based on the enhanced radiation monitoring signal, high-precision prediction of nuclear radiation dose spatial distribution is carried out through a deep probabilistic neural network model; according to the high-precision prediction result, in combination with a nuclear accident severity level standard, a radiation alert evaluation result and early warning information are generated, short-term radiation fluctuation can be captured, a long-term change trend can be identified, and the understanding ability of the system to a complex radiation field is greatly improved.

The invention belongs to the technical field of nuclear radiation measurement, and relates to a liquid flash TDCR multi-nuclide beta spectrum analysis method and system based on artificial intelligence. The method comprises the following steps: constructing a numerical model of a liquid flash detector spectrometer by using a Monte Carlo technology to simulate the energy spectrum response of a single nuclide under different quenching conditions; constructing a training database by adopting a parameterized data synthesis algorithm; constructing a multi-task mixed spectrum analysis neural network model; carrying out model training by utilizing the constructed database; and inputting an actual measurement spectrogram, and outputting the multi-nuclide absolute activity, the detector efficiency and the decomposition energy spectrum contribution curve in real time by using the trained neural network model. According to the method, differential distribution characteristics and quenching response curve characteristics of the beta continuous energy spectrum are creatively fused, a neural network architecture with physical mechanism constraints is constructed, and liquid flash TDCR multi-nuclide energy spectrum characteristic decoupling and accurate activity solving are achieved under the unknown quenching condition.

The invention relates to the technical field of nuclear radiation imaging, in particular to a radiation array detector, a back scattering imaging system and a back scattering imaging method. The radiation array detector comprises an X-ray photon absorption structure which comprises high-strip-shaped scintillators and low-strip-shaped scintillators which are alternately arranged, the high-strip-shaped scintillators are used for detecting back scattering X-ray photons incident at all angles, the low-strip-shaped scintillators are used for accurately determining the incident direction of the X-ray photons through the collimation effect, and the high-strip-shaped scintillators and the low-strip-shaped scintillators are used for detecting the incident direction of the back scattering X-ray photons; after X-rays enter the photon absorption structure, the high-strip-shaped scintillators and / or the low-strip-shaped scintillators receiving X-ray photons generate scintillation photons. The silicon photomultiplier array is connected with the high strip-shaped scintillator and the low strip-shaped scintillator through a light guide and is used for converting scintillation photons into photoelectric signals; and the position and energy information coding circuit is used for carrying out position and energy information coding on the photoelectric signals generated by the silicon photomultiplier array. According to the invention, the detection efficiency and the direction identification capability of the back scattering X-ray can be effectively improved.

The invention provides a nuclear radiation diffusion analysis method based on a Gaussian mixture atmospheric diffusion model. The method comprises the steps that nuclear facility source item parameters are acquired; integrating meteorological, geography, remote sensing and radiation monitoring data by using a heterogeneous data fusion engine, extracting atmospheric turbulence, terrain and building interference characteristics and source item parameters, and forming a dynamic input parameter set; constructing an unsteady state diffusion model containing a multi-modal distribution function, processing features, obtaining a mixed distribution model, and correcting the mixed distribution model; predicting spatial and temporal distribution of radiation pollutants, and generating multi-scale diffusion field simulation; and optimizing a diffusion path, and generating a three-dimensional risk field. According to the method, multi-source data are integrated, an unsteady state diffusion model is constructed, Gaussian component weights are dynamically adjusted, the model is corrected by using real-time data, and a geographic information system is coupled to carry out spatial constraint optimization. And through multi-scale feature coupling, dynamic parameter adjustment and geographic space constraint correction, the depicting capability of the atmospheric diffusion model is remarkably improved, and the nuclear radiation diffusion prediction precision is greatly improved.

The invention relates to the technical field of nuclear radiation monitoring, in particular to a water body total radioactivity and nuclide on-line measurement system which comprises a gamma detector, a beta detector, an alpha detector and a water treatment component, the water treatment component extracts a water body sample and processes the water body sample, and then the water body sample passes through the gamma detector, the beta detector and the alpha detector; the gamma detector is arranged in a first shielding body, and the beta detector and the alpha detector are arranged in a second shielding body; the water treatment assembly provided by the invention is responsible for extracting and treating a water body sample, so that the water body sample sequentially passes through various detectors and a gamma detector to obtain a gamma energy spectrum of the water body sample, and a beta detector and an alpha detector respectively obtain beta and alpha total activity of the water body sample, and accurate detection of different types of radiation is realized.

The invention discloses a preparation method of a polydopamine modified boron carbide-zinc methacrylate coordination reinforced rubber-based radiation protection composite material, and relates to the technical field of radiation protection materials. The method comprises the following steps: dispersing boron carbide in a triaminomethane buffer solution containing dopamine, and carrying out surface polymerization reaction to obtain polydopamine modified boron carbide; and mixing the polydopamine modified boron carbide, zinc methacrylate and a rubber matrix, and vulcanizing to obtain the polydopamine modified boron carbide-zinc methacrylate coordination enhanced (zinc is coordinated with nitrogen / oxygen and the like on the surface of the modified boron carbide) rubber-based radiation protection composite material. Through multiple effects of coordination enhancement, chemical crosslinking and the like, the material has excellent neutron shielding performance and tensile property, the preparation method is simple, the cost is low, and the material has a wide application prospect in the field of nuclear radiation protection.

The embodiment of the invention relates to the field of exploration or detection by applying nuclear radiation, in particular to a method for determining a uranium metallogenic area of a to-be-surveyed area, which comprises the following steps of: determining natural gamma logging data and energy spectrum logging uranium content data of the to-be-surveyed area; determining the positions of a plurality of drill holes of the to-be-surveyed area; obtaining a rock core sample of one of the determined drill holes; determining uranium contents at different depths according to the rock core sample; determining the relationship between the uranium content and the energy spectrum logging uranium content data of the drill hole and the relationship between the energy spectrum logging uranium content data and the natural gamma logging data so as to determine the relationship between the uranium content and the natural gamma logging data; and determining a natural gamma logging threshold value of the uranium metallogenic area so as to determine the uranium metallogenic area of the area to be surveyed. According to the method provided by the embodiment of the invention, the natural gamma logging threshold value of the uranium metallogenic area can be accurately determined, so that the uranium metallogenic area of the area to be surveyed can be accurately determined, and the exploration cost is greatly reduced.

The invention discloses a method for selecting and triggering gamma instant radiation pulse events, and belongs to the technical field of nuclear radiation detection. The method comprises the following steps: carrying out normalization preprocessing on an original gamma pulse radiation time spectrum; s time-frequency transformation is carried out on the preprocessed data, and time-frequency features are extracted; optimizing parameters of the frequency threshold and the amplitude threshold after S time-frequency transformation by adopting a deep reinforcement learning model to obtain an optimal frequency threshold and an optimal amplitude threshold; performing filtering processing on the signal of the S time-frequency conversion result, and separating noise from an effective signal; and searching a pulse radiation event for the filtered signal by applying a morphology-based peak searching method, and positioning the position and the characteristic of a real gamma instant radiation pulse event. According to the method, time-frequency analysis is carried out through S time-frequency transformation, the problem that the frequency of an analysis window cannot be adjusted through short-time window Fourier transformation is solved, the method has better frequency resolution and phase retention characteristics, and gamma pulse signal characteristics can be represented more accurately.

The invention discloses a fast thermal neutron and gamma ray multi-mode detector, and relates to the technical field of nuclear radiation detection, and the detector comprises a detector housing, and the interior of the detector housing is connected with a fast neutron detection unit, a thermal neutron detection unit and a gamma ray detection unit. The gamma ray detection unit is located between the fast neutron detection unit and the thermal neutron detection unit; and an insulating separation unit is connected between two adjacent detection units. The detector can detect fast neutrons, thermal neutrons and gamma rays in the same equipment at the same time, structures such as a cadmium thermal neutron shielding layer and a fast neutron moderation layer do not need to be added, the size of the detector can be greatly reduced, and the detector has the advantages of being compact in structure, stable in performance, wide in energy measurement range, wide in fluence rate measurement range and the like. The ultrahigh-energy high-flux neutron measurement with the neutron energy at least covering # imgabs0 # and the neutron fluence rate at least covering # imgabs1 # can be realized.

The invention discloses a nuclear radiation resistant heat-insulating protective coating for steam pipelines and a preparation method thereof. The coating comprises a surface layer and a bottom layer; the surface layer comprises 30 to 50 parts of a surface layer base, 10 to 30 parts of pigments and fillers, 5-10 parts of metal powder, 18 to 20 parts of a curing agent and 18 to 20 parts of a diluent; the bottom layer comprises 10 to 30 parts of a bottom layer base, 30 to 50 parts of pigments and fillers, 5-10 parts of metal powder, 18 to 20 parts of a curing agent and 18 to 20 parts of a diluent; wherein the surface layer base comprises acrylic modified organic silicon resin; the bottom layer base comprises water glass; the pigments and fillers comprise enamel powder, ceramics and auxiliary fillers; the auxiliary fillers comprise one or more of mica, iron oxide, zinc titanate, fluoropolymer and borosilicate; the coating of the invention can effectively insulate and protect the steam pipeline in a high temperature and nuclear radiation environment, thereby extending the service life of the steam pipeline and improving the safety and reliability of the nuclear power plant.

The invention relates to the field of nuclear radiation detection, and provides a Compton camera image reconstruction method and electronic equipment, and the method comprises the steps: collecting multiple event data generated by a target radioactive source in multiple events; for each event in the multiple events, reconstructing the back-projection cone based on a back-projection algorithm according to the event data of the event to obtain coordinate representation of the spatial position of the back-projection cone; determining an initial coordinate of the target radioactive source according to the coordinate representation of the plurality of back projection cones of the multiple events in the plane where the target radioactive source is located; for each event in the multiple events, determining the weight of the event based on the initial coordinate of the target radioactive source and the event data of the event; and utilizing a model based on a maximum likelihood expectation maximum algorithm to perform iterative reconstruction based on the weight of multiple events to obtain a reconstructed image. By means of the method, the spatial resolution and reconstruction efficiency of the image formed by the Compton camera system can be improved.

The invention provides a radiation shielding multi-objective optimization design method based on a Bayesian neural network, and the method is characterized in that the method comprises the following steps: S1, obtaining sample data; s2, network construction and evaluation; s3, robust design optimization is carried out; according to the method, cognitive uncertainty in the modeling process of an agent model is quantified by using a loss function based on variational inference and KL divergence derivation, a nuclear radiation shielding calculation agent model considering uncertainty factors is obtained, and radiation shielding calculation is performed on an objective function in multi-objective optimization design through the constructed agent model. And a Pareto optimal solution set with certain robustness is obtained in combination with robust optimization design. According to the method, prior distribution is added to the weights of a neural network model, then the change conditions of the weights when data are given are obtained to measure the cognitive uncertainty in radiation shielding simulation, and the robustness of an optimization result is improved.

The invention discloses a current sampling circuit for collecting signals of a nuclear radiation detector and a high-voltage power supply, the current sampling circuit is arranged in the nuclear radiation detector comprising the high-voltage power supply, the high-voltage power supply comprises a voltage transformation assembly, and the current sampling circuit comprises a sampling resistance adjustable collecting unit and a resistance adjusting unit. The sampling resistance value adjustable acquisition unit is connected with the secondary side of the voltage transformation assembly, and the sampling resistance value adjustable acquisition unit is used for acquiring the voltage of the secondary side of the voltage transformation assembly and outputting the acquired voltage. And the resistance value adjusting unit is connected with the sampling resistance value adjustable acquisition unit and is used for controlling the sampling resistance value of the sampling resistance value adjustable acquisition unit to dynamically change until the sampling resistance value is stable according to the first voltage. Wherein the current of the nuclear radiation detector is the ratio of the target voltage to the target resistance value, the target resistance value is the sampling resistance value when the sampling resistance value adjustable acquisition unit adjusts the resistance value to be stable, and the target voltage is the voltage collected by the sampling resistance value adjustable acquisition unit under the target resistance value.

The invention belongs to the technical field of nuclear radiation measurement, and particularly relates to an automatic low background alpha and beta detection device. The device comprises a cylindrical lead chamber, a main detector, an anticoincidence detector, a first photomultiplier, a second photomultiplier and a conveying device, the conveying device is arranged on the outer side of the lead chamber and used for conveying a sample to be detected into the cylindrical lead chamber for detection, and the main detector and the anticoincidence detector are located in the cylindrical lead chamber and used for detecting the sample to be detected. The main detector and the anticoincidence detector lead out signals through the first photomultiplier tube and the second photomultiplier tube respectively. The problem of total alpha and total beta radioactivity automatic detection can be solved, and multiple samples can be detected at a time.

The invention belongs to the technical field of semiconductor detectors, and particularly relates to a whole process simulation method and system for response of a semiconductor nuclear radiation detector. According to the method, through cooperative operation of a detector working parameter setting module, a carrier transport simulation module and a detection system electronics response module, whole-process response prediction of the semiconductor detector from radiation interaction to electronics output can be realized under different carrier transport characteristics and device structure conditions; according to the method, the carrier drift process is simulated in a small-step iteration mode, accurate reconstruction of a carrier drift track can be synchronously achieved, CSA signals and main amplifier forming signals can be continuously generated in real time, simulation output of an energy spectrum is finally completed, and therefore core performance indexes of a detector are comprehensively reflected. The method is wide in applicable semiconductor material range and device structure, the main amplifier module type can be flexibly configured, the overall simulation process is simple, convenient and efficient, and the method has good universality and engineering application value.

The utility model provides an irradiation-resistant underwater camera with a reflection lens, which comprises a metal middle cylinder main body, and the front end of the metal middle cylinder main body is hermetically connected with a front cover of protective glass with a lens. An imaging structure composed of an electric focusing lens, a lens reflecting prism, a photoreceptor, a circuit main board, a circuit auxiliary board and an imaging module is arranged in the metal middle cylinder body, the imaging structure is fixedly connected with a rear baffle through a lens fixing block and an inner support, and the tail end of the metal middle cylinder body is connected with a rear cover with a watertight connector in a sealed mode. The beneficial effects of the utility model are that the whole body employs a waterproof design, the circuit main board, the circuit auxiliary board and the imaging module all employ an irradiation-resistant circuit board structure, can be applied to an underwater environment with nuclear radiation for a long time, changes the layout of the photoreceptor and the imaging module, adds a lens reflecting prism as an auxiliary structure, improves the imaging structure, and improves the imaging efficiency. The underwater camera shooting imaging effect and the reduction of the width and the size of the camera in the production process are facilitated.

The invention relates to the field of composite material prediction based on a specific model, and discloses a mechanical property simulation method for simulating defects of a carbon fiber composite material based on Monte Carlo-finite element, which comprises the following steps: constructing a carbon fiber composite material RVE model in Monte Carlo software, setting an irradiation physical reaction process, and carrying out neutron irradiation analogue simulation. The method comprises the following steps: obtaining internal void defect information of a material, constructing a finite element RVE model containing void defects in finite element software, obtaining an elastic constant matrix of the whole RVE model, constructing a macroscopic tensile finite element model, carrying out material parameter setting and simulation boundary condition setting on the macroscopic model, and carrying out macroscopic tensile simulation to obtain simulation mechanical data. According to the method, the problems of high cost and long time of an irradiation experiment and a mechanical experiment are solved, a technical basis is provided for reliability evaluation research of the carbon fiber composite material in a nuclear radiation scene, and a large amount of time and economic cost are saved.

The invention relates to the technical field of nuclear radiation detection management, and discloses a nuclear radiation detection management system based on artificial intelligence, comprising: a dynamic sensing module which detects nuclear radiation through quantum sensing to obtain radiation data, captures NV color center fluorescence intensity, analyzes to obtain gamma ray dose rate, constructs a nanoscale olfactory receptor simulation structure, and sends the radiation data to a control module; radioactive gas is detected and cooperatively monitored; the reasoning calculation module is used for analyzing space-time correlation based on radiation data, optimizing algorithm to accelerate result output, adjusting calculation complexity by calculating dynamic weight distillation, and correcting data transmission in real time; the decision management module is used for constructing a four-dimensional causal graph based on the radiation data, performing intervention simulation, evaluating a decision long-term effect, screening an optimal decision, and performing adversarial training based on historical repair case data; and the fusion cooperation module is used for establishing a cross-mechanism federated learning framework, carrying out hash operation on the radiation data, and establishing an NFT (Network Fourier Transform) on a block chain through an intelligent contract for query, verification and transaction.

The invention discloses a one-way automatic valve welding seam cutting method and a one-way automatic valve welding seam cutting device. The one-way automatic valve welding seam cutting method comprises the following steps that S1, a safety insurance mechanism is unlocked; s2, the cutting height is adjusted through an automatic lifting mechanism; s3, the clamping mechanism clamps the valve; and S4, a ratchet wheel automatic cutting mechanism is used for cutting the valve welding seam and comprises a machine pedestal, one side of the machine pedestal is connected with an automatic lifting mechanism, and the machine pedestal is provided with an electric driving mechanism used for changing the movement direction and a clamping mechanism used for clamping the valve. The electric driving mechanism is connected with and provides power for the automatic ratchet wheel cutting mechanism for automatically cutting the welding seam of the valve, a working method of a ratchet wheel mechanism is adopted, one-way cutting of the welding seam of the valve is achieved, and the electric driving mechanism is used for driving a ratchet wrench to continuously rotate within a certain angle so that the welding seam of the sealing valve can be automatically cut by a cutter. And the time that workers need to be in high-concentration nuclear radiation during cutting is greatly shortened.

The invention belongs to the technical field of nuclear radiation field monitoring, and discloses a radiation field and administrative division overlapping design method, which comprises the following steps of: generating a three-dimensional terrain model; performing real-time rendering and optimization on the model; calculating the grid concentration of the radiation field; and superposing the radiation field data with the GIS administrative region. According to the method, the administrative division boundary data and the radiation field grid data are subjected to cross processing, and the name of the administrative division covered by the radiation field and the number of affected population are given. And the influence range and the change trend of the radiation field can be reflected in a three-dimensional scene more visually. The problem that in a traditional method, the visualization performance is poor due to the fact that a radiation field does not support multi-dimensional display can be solved, and technical support is provided for nuclear emergency command decision making under a nuclear accident.

The invention discloses a miniature high-voltage module for a nuclear radiation detector. The miniature high-voltage module comprises a Boost chip circuit, a driving circuit and a voltage doubling rectifying circuit, the input end of the Boost chip circuit is connected with a power supply, the output end of the Boost chip circuit is connected with the driving circuit, and the Boost chip circuit is used for boosting the voltage input into the input end of the Boost chip circuit and outputting the boosted voltage to the driving circuit; the driving circuit is used for providing bidirectional current for the voltage doubling rectifying circuit based on the voltage output by the output end of the Boost chip circuit; and the voltage doubling rectifying circuit is used for amplifying the voltage output by the driving circuit and outputting a target voltage meeting the detection condition of the nuclear radiation detector. According to the module, the Boost chip circuit is adopted, the size of the miniature high-voltage module can be optimized, meanwhile, the miniature high-voltage module is additionally provided with the driving circuit, the requirement of some special detectors for large current is met, and the adaptation degree between the miniature high-voltage module and the nuclear radiation detector can be improved.

The invention provides a debugging control system and method for an electrical refrigeration high-purity germanium detector, and the method comprises the steps: determining the escape capability of an electron hole pair in the electrical refrigeration high-purity germanium detector through an initial bias value and each energy resolution, and determining a bias critical value of complete separation of the electron hole pair based on the escape capability; determining a first boost gradient of bias voltage increase according to the bias voltage critical value and each leakage current; the detection responsivity of the high-voltage electric field under each bias voltage is determined, and then the noise disturbance quantity of the high-voltage electric field is determined according to all the detection responsivity; and performing high-voltage compensation on the first boost gradient based on the noise disturbance quantity to obtain a second boost gradient of bias voltage increase when the electron hole pair of the electrical refrigeration high-purity germanium detector is completely separated, and taking the second boost gradient as a bias voltage debugging result of the electrical refrigeration high-purity germanium detector. Based on the scheme, multi-gradient bias voltage debugging of bias voltage increase in the electrical refrigeration high-purity germanium detector can be realized, and the nuclear radiation detection sensitivity of the electrical refrigeration high-purity germanium detector is improved.

The nuclear-radiation-resistant halogen-free low-smoke flame-retardant polyolefin irradiation sheath material comprises the following raw materials in parts by weight: 30-50 parts of a polar copolymer, 10-30 parts of an elastomer, 10-30 parts of polyethylene, 5-15 parts of a grafting material, 120-180 parts of a flame retardant, 20-40 parts of a flame-retardant synergist, 1-2 parts of a lubricant, 3-5 parts of an antioxidant and 1-2 parts of a dispersant. The polar copolymer comprises an ethylene-vinyl acetate copolymer and the like; the elastomer comprises aluminum hydroxide and the like; the flame-retardant synergist comprises zinc borate and the like; the lubricant comprises polyethylene wax and the like; the antioxidant comprises tetra [beta-(3, 5-di-tert-butyl-4-hydroxyphenyl) propionic acid] pentaerythritol ester and the like; and the dispersing agent is a silane coupling agent. The preparation method of the nuclear-radiation-resistant halogen-free low-smoke flame-retardant polyolefin radiation sheath material comprises the following steps: mixing and granulating the flame-retardant synergist, the antioxidant and part of the polar copolymer to obtain a material B; mixing, screw extrusion, shearing and stirring are carried out on the remaining raw materials and the material B, and finally extrusion granulation is carried out to obtain a finished product material.

The invention relates to an optical fiber coupling type focusable laser cutting device. According to the device, a laser transmitter transmits laser through an input optical fiber; the laser receiving module comprises a mounting seat, an optical fiber base, a transmission mechanism and a focusing mechanism, the focusing mechanism drives the optical fiber base to move in the axial direction through the transmission mechanism, and motor-free focusing in the nuclear radiation environment is achieved; the laser conduction module comprises a parabolic reflector for collimating and focusing the laser; according to the laser cutting device, the focusing technology depending on a motor in the prior art is converted into full-mechanical transmission focusing design, the failure risk of electronic elements such as the motor in the radiation environment is avoided, and through cooperation of the focusing mechanism, the transmission mechanism and the limiting pin, the laser cutting efficiency is improved. The high-precision and high-reliability focusing function is achieved, and the laser cutting device which is good in radiation resistance, high in long-term operation stability and long in service life is achieved in the nuclear radiation environment.

The invention relates to the technical field of nuclear radiation monitoring, and provides a multifunctional signal processing device for nuclear measurement, which comprises three signal conditioning modules respectively used for conditioning signals of three nuclear measurement detectors, the signal processing device comprises a signal processing module and a signal processing module, weak signals output by the signal processing module are shielded by a tri-coaxial cable and a connector and then enter corresponding channels to be amplified, filtered, subjected to gain adjustment and signal conditioning and then subjected to isolated output, the signal processing module further comprises a signal processing module, and the conditioned signals are sampled and counted by a high-speed ADC and a counter to form digital signals. The multifunctional signal processing device for nuclear measurement is used for processing output signals of various detectors of a nuclear measurement system, can carry out digital processing on weak pulse signals, weak current signals and stacked and overlapped charge pulses, and is simple and efficient.

The invention provides a dynamic PSD threshold value correction method, device and equipment suitable for digital pulse waveform discrimination, and relates to the technical field of nuclear radiation detection.The method comprises the steps that a current PSD-energy two-dimensional spectrum is obtained through a nuclear radiation detecting instrument, counts in a target energy range in the current PSD-energy two-dimensional spectrum are removed, and the current PSD-energy two-dimensional spectrum is obtained; converting into a one-dimensional PSD spectrum by using a preset formula; determining the position of the maximum peak and the full width at half maximum in the one-dimensional PSD spectrum, determining a PSD threshold value, and resetting the target PSD value range according to the PSD threshold value; and obtaining the target PSD-energy two-dimensional spectrum again, carrying out statistics on the discrimination target ray counting value and the total counting value, and determining a main target ray counting value according to a difference value between the total counting value and the discrimination target ray counting value so as to determine a main target ray counting rate and a discrimination target ray counting rate. By regularly and automatically analyzing the PSD-energy two-dimensional spectrum and dynamically adjusting the PSD threshold value, different particles can be more accurately discriminated, and the particle detection accuracy and efficiency are improved.

The invention relates to the technical field of nuclear reactors, and provides a nuclear reactor piezoelectric sensor sensitive material optimization method and device and a medium, and the method comprises the steps: 1, determining an initial sensitive material sample based on a sensitive material template and an initial element doping scheme; 2, performing an irradiation experiment on the initial sensitive material sample, and determining irradiation parameters corresponding to the initial sensitive material sample based on an experiment result; 3, determining the average parameter change rate of the sample based on the irradiation parameters corresponding to the plurality of initial sensitive material samples and the high-temperature performance parameters corresponding to the plurality of initial sensitive material samples subjected to the irradiation experiment, and judging whether the average parameter change rate of the sample is smaller than a preset threshold value or not; if yes, determining the initial sensitive material sample as a target optimization sensitive material; and if not, adjusting the initial element doping scheme, and returning to the step 1. According to the embodiment, the piezoelectric coefficient of the piezoelectric sensitive material in a high-temperature nuclear radiation environment is improved, and the fault monitoring precision of key equipment of a nuclear reactor is improved.