373 results about "Nuclear radiation" patented technology

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 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 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 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 invention relates to the technical field of materials for anti-nuclear radiation clothes, in particular to ethylene propylene rubber for anti-nuclear radiation clothes and a preparation method of the ethylene propylene rubber. A composite multi-walled carbon nanotube subjected to pretreatment; an accelerant; a fiber; a plasticizer; an anti-aging agent; stearic acid; through an innovative raw material formula and a corresponding preparation process, the novel ethylene propylene rubber material for the nuclear radiation prevention clothing is mainly researched and developed. In the aspect of raw materials, the radiation shielding performance of the ethylene propylene rubber is remarkably improved by introducing the specially pretreated composite multi-walled carbon nanotubes and reasonably matching the nano zinc oxide. Meanwhile, the specific dosage ratio of the ethylene propylene rubber, the accelerant, the fiber, the plasticizer and other raw materials ensures that the product has excellent shielding performance and also has good weather resistance, flexibility and comfort.

The invention discloses a dose rate measurement method, device and equipment based on Poisson maximum likelihood estimation, and a storage medium, and the method comprises the steps: obtaining and preprocessing environment nuclear radiation monitoring data, and obtaining a fusion data sequence; dividing the fused data sequence into a plurality of time windows and determining an envelope spectrum sequence; performing radiation dose rate estimation on the envelope spectrum sequence through a Poisson maximum likelihood estimation method to obtain a preliminary dose rate estimation value; determining an environment correction factor according to the temperature data sequence, the humidity data sequence and the air pressure data sequence; correcting the initial dose rate estimation value to obtain a corrected dose rate estimation value; and inputting the corrected dose rate estimated value and the average dose rate and the maximum dose rate in each time window into a support vector machine model for prediction to obtain a future nuclear radiation dose rate prediction result, and updating the optimal estimated value of the dose rate in real time by introducing a Poisson maximum likelihood estimation algorithm. The accuracy and response speed of dose rate estimation are improved.

The invention discloses a convolutional neural network and multi-source data fusion-based nuclear radiation on-line monitoring method, which comprises the following steps of: acquiring laser radar point cloud data, a radiation dose rate and a radiation image of a monitoring area by adopting an unmanned aerial vehicle, and de-noising the radiation image by adopting a double-branch convolutional neural network; determining the track position of the unmanned aerial vehicle according to the laser radar point cloud and the de-noised image; performing space-time registration on the radiation dose rate and the track position of the unmanned aerial vehicle to form a data set, and obtaining a continuous radiation field of the monitoring area by adopting Kriging interpolation; according to the continuous radiation field, an L-BFGS-B algorithm is adopted to carry out minimization solution on a loss function with the radiation source position as an optimization variable, and position coordinates of the radiation source are obtained; performing data cleaning on the radiation dose in the continuous radiation field, and then performing multi-dimensional feature extraction to obtain a feature vector; and inputting the feature vectors into a plurality of prediction models to obtain a plurality of predicted radiation doses, and carrying out weighted fusion to obtain a predicted dose rate of the radiation source.

The invention discloses a radioactive waste liquid surface pollution multipoint array detection system and method, and relates to the technical field of nuclear radiation detection. The radioactive waste liquid surface pollution multipoint array detection system comprises a main body fixing frame, a mobile control device, a detector and an upper computer, a plurality of mounting holes arranged in a planar array are formed in the main body fixing frame; the movement control device controls the main body fixing frame to move; the plurality of detectors are mounted in the mounting holes of the main body fixing frame; the upper computer is used for regulating and controlling parameters of the CMOS sensor and storing, displaying, analyzing and processing frame images. The radioactive waste liquid storage tank liquid level pollution monitoring method is applied to a radioactive waste liquid surface pollution multipoint array detection system and is used for monitoring alpha and beta pollution areas of a radioactive waste liquid storage tank liquid level. The whole liquid level area of the radioactive waste liquid storage tank is covered at a time through the detachable detector group arranged in the plane array, and a pollution distribution panorama can be obtained through single-time measurement.

The invention discloses a nuclear radiation energy spectrum double-domain collaborative optimization method and a related device, and belongs to the technical field of nuclear radiation measurement, and the method comprises the steps: obtaining an original distortion pulse sequence generated by nuclear radiation measurement; a double-domain collaborative energy spectrum optimization model is constructed, the double-domain collaborative energy spectrum optimization model comprises a pulse domain repair model and an energy spectrum domain reconstruction model which are arranged in parallel, and the pulse domain repair model is used for performing pulse-by-pulse repair on the amplitude and the arrival time of the original distorted pulse sequence and outputting a repaired pulse sequence; the energy spectrum domain reconstruction model is used for converting the repaired pulse sequence into an energy spectrum diagram; in the training process of the double-domain collaborative energy spectrum optimization model, the pulse domain repair model and the energy spectrum domain reconstruction model share the back propagation gradient of the joint loss function, so that bidirectional closed-loop collaborative optimization of the pulse repair model and the energy spectrum reconstruction model can be realized, the problem of step-by-step error amplification caused by a traditional serial processing mode is avoided, and the performance of the system is improved. And the authenticity and the accuracy of the output energy spectrum are obviously improved.

The invention discloses a nuclear accident dynamic safe operation time assessment method and system based on data fusion, relates to the technical field of nuclear radiation protection, and solves the technical problems that the safe operation time is not accurate enough and dynamic dose assessment is difficult in nuclear accident emergency response. According to the technical scheme, nuclear accident prediction data and site real-time monitoring data are fused, a data assimilation fusion algorithm and an intelligent analysis model are combined, the radiation dose and environmental conditions of an accident site are comprehensively evaluated, and safety operation time and risk levels of different areas are dynamically calculated and updated; by considering the building shielding effect and supporting the federated learning framework, the cooperative evaluation of multiple monitoring points is realized, so that the operation time evaluation precision and decision-making efficiency in the nuclear accident emergency response are greatly improved. Finally, operation suggestions can be fed back and updated in real time, and the real-time performance and accuracy of emergency command decisions are ensured.

The invention discloses a silicon photomultiplier and a preparation method thereof, belongs to the technical field of semiconductor device processing, and aims to solve the problems of lattice damage, channel effect, interface defects and the like caused by single-time high-dose ion implantation in the traditional process. Through the innovative processes of dose grading ion implantation, stepped cooling annealing, Gepre-amorphization processing, atomic layer deposition passivation and the like, the dark counting rate of the device is remarkably reduced, and the photon detection efficiency and the avalanche gain stability are improved. The prepared silicon photomultiplier comprises an optimally designed doped region and an Al2O3 / SiNx composite passivation layer, has excellent detection performance in a blue-violet light band, and can be widely applied to high-sensitivity detection fields such as biomedical imaging, nuclear radiation detection and laser radar.

The present invention relates to the field of nuclear technology. A container for storing, transporting, and disposing of solid radioactive waste comprises a canister made of reaction-sintered silicon carbide with a free silicon content of 3% to 30% by weight, with a fumed silicon carbide layer deposited on the canister's surface. The canister's outer layer is made of metal foam with an open porosity of 60% to 70% and a pore size of 5 mm to 6 mm. The pores are filled with dispersed boron carbide powder of 40 to 50 μm in diameter, thereby protecting the environment from nuclear radiation emitted by high-level radioactive waste. A stainless steel cylinder with a thickness of 1 mm to 1.5 mm, intended to contain radioactive waste, is placed within the silicon carbide canister. A 5 mm gap between the inner surface of the silicon carbide canister and the stainless steel cylinder is filled with boron carbide powder, thereby protecting the environment from nuclear radiation emitted by high-level radioactive waste. The silicon carbide canister is sealed with a lid made of silicon carbide using a reaction welding method. The metal foam used as the metal foam with an open porosity is selected from the group consisting of titanium, aluminum, and copper. The present invention can increase the strength of containers for solid radioactive waste.

The invention provides a three-dimensional reconstruction method and system in a nuclear irradiation environment, and relates to the technical field of computer vision. According to the method, a Swin Transformer network is adopted to perform feature extraction processing on an original image containing radiation noise, a constructed three-dimensional reconstruction network adopts a U-Net architecture, reservation of detail features is ensured through an encoding-decoding process, after radiation noise processing is completed, an FFB6D network is introduced to directly process a nuclear radiation environment reconstruction image, and the method has the advantages that the method is simple and convenient to operate and high in practicability. The accuracy and the stability of pose estimation under severe visual conditions are improved, and a geometric basis is provided for three-dimensional reconstruction. Model selection and optimization are carried out on all the modules adopted by the system according to the characteristics of the nuclear irradiation environment, technical resultant force is formed, a high-performance and full-automatic three-dimensional reconstruction system specially designed for the extremely severe visual environment such as nuclear irradiation is finally constructed, and the precision, robustness and practicability of three-dimensional perception in the field are remarkably improved.

This invention relates to the field of nuclear radiation detection technology, and more particularly to an energy spectrum processing method for a quasi-hemispherical CdZnTe detector. The method includes: acquiring the raw signal collected by the quasi-hemispherical CdZnTe detector; normalizing the amplitude of the raw signal from the baseline to the highest point during the rise phase; dynamically selecting multiple energy thresholds; performing rise time discrimination on the normalized signal within each energy threshold; filtering out signals with rise times greater than RTflag and determining the rise time range corresponding to that energy threshold; constructing an intermediate energy spectrum corresponding to each energy threshold based on the signals with rise times greater than RTflag and the rise time range; and post-processing the intermediate energy spectrum to obtain the target energy spectrum corresponding to each energy threshold. This invention combines energy threshold discrimination, rise time discrimination, and energy spectrum post-processing algorithms to stably improve the energy resolution of the quasi-hemispherical CdZnTe detector for 662 keV gamma rays from the conventional 2%~3% to less than 1%.

The application discloses a double-gas-chamber neutron detector, belonging to the technical field of nuclear radiation detection and particle detection, comprising a gadolinium film neutron conversion layer, two time projection chamber (TPC) modules and an optional energy quantifier module. After capturing thermal neutrons, the gadolinium film generates multi-state particles, and the two TPC modules realize 4π solid angle neutron detection through electronic signal coincidence. The application replaces the scarce 3 He with gadolinium, combines the track reconstruction capability of the double TPC module, significantly improves the neutron detection efficiency and signal-to-noise ratio, and is suitable for nuclear reactor monitoring, industrial material analysis, agricultural moisture detection and deep space exploration and other fields. Through electronic-gamma coincidence measurement and mode recognition, high-precision neutron signal reconstruction and environmental background suppression are realized.

The application provides a flame-retardant composite shielding material and a preparation method and application thereof, and belongs to the technical field of nuclear radiation shielding materials. The flame-retardant composite shielding material comprises the following components in parts by mass: 10-20 parts of high-density polyethylene, 68-81 parts of lead, 0.5-4 parts of boron carbide and 9-20 parts of a flame retardant. By adopting high-density polyethylene, lead, boron carbide and a flame retardant and controlling the mass fraction of each component, the heat resistance, flame retardance and shielding performance of the flame-retardant composite shielding material can be improved.

The utility model discloses a beta radiation detection device based on an aluminized plastic scintillator detector, and belongs to the technical field of nuclear radiation measuring instruments. The photomultiplier comprises a stainless steel shell, an aluminum shell is arranged in the stainless steel shell, an aluminized plastic scintillator is arranged at the top of the aluminum shell, a photomultiplier is arranged in the aluminum shell, and the photomultiplier is located at the bottom of the aluminized plastic scintillator. According to the utility model, through the arrangement of the aluminum-plated plastic scintillator, the aluminum layer is directly deposited on the plastic scintillation sheet through the magnetron sputtering process, so that the traditional aluminum-plated film is effectively replaced, the structure of the detection device is further simplified, the production cost is also obviously reduced, and the aluminum layer and the plastic scintillator can be tightly combined through the magnetron sputtering process; compared with the prior art, extra assembling steps are avoided, manpower and material consumption is reduced, production efficiency is improved, and the durability of the detector is enhanced due to the fact that the aluminum layer is directly deposited on the surface of the plastic scintillator.

The utility model discloses a spiral constant flow probe for radon survey meter soil survey belongs to nuclear radiation detection technical field, including intermediate connecting piece, and the bottom end detachable connection of intermediate connecting piece has the gas guide main pipe, and the upper surface of intermediate connecting piece is provided with the flowmeter connecting hole and short stick connecting hole, and the bottom end of intermediate connecting piece is the circular truncated cone structure and is provided with the outer thread, and the gas flowmeter is connected with radon survey meter still, and the bottom end of intermediate connecting piece is the circular truncated cone structure and is provided with the outer thread, and the utility model sets up and has the intermediate connecting piece of thread, and the leakproofness between intermediate connecting piece can pass through the thread promotion and the detection soil, to make the measurement result more accurate.

This invention relates to the fields of nuclear detection electronics and radiation signal processing technology, specifically to an intelligent analysis system and method for nuclear radiation data. The system includes: acquiring a discrete voltage sequence output by the detector; marking pulse signals as clean pulses and calculating the real-time decay constant; calculating the net signal amplitude using a digital twin state-space recursive model; determining the real-time count rate based on the net signal amplitude and calculating the dynamic time window width based on the real-time count rate; discretely accumulating the net signal amplitude based on the dynamic time window width to generate a single-particle physical energy value; determining the measured peak position based on the single-particle physical energy value and generating a gain adjustment coefficient by combining the measured peak position with the real-time decay constant; and outputting a gain control signal based on the gain adjustment coefficient. This invention ensures precise synchronization between the subsequent calculation model and the current physical state of the detector, thereby significantly improving the physical authenticity and accuracy of energy spectrum analysis under varying temperature conditions.

A self-powered nuclear radiation detector. The self-powered nuclear radiation detector includes a cable assembly, a temperature compensation assembly, and a metallic outer sheath. The cable assembly includes a metallic signal lead, an insulative material surrounding the metallic signal lead, and a metallic sheath surrounding the insulative material. The temperature compensation assembly includes a second metallic signal lead, a second insulative material surrounding the second metallic signal lead, and a second metallic sheath surrounding the second insulative material. The metallic outer sheath surrounds the cable assembly and the temperature compensation assembly.

The nuclear radiation environment multi-target point inspection path planning mathematical modeling method, the grid map of the nuclear radiation environment is prior information, each grid in the grid map contains radiation field information and obstacle information;The method is as follows: considering the path length and the cumulative radiation dose and the turning energy consumption, the inspection path evaluation model and the pair path cost calculation model are established respectively.The present application is aimed at the mobile robot MTIPP problem in indoor nuclear environment, considering the path length and the cumulative radiation dose and the turning energy consumption, a double-layer mathematical model is established, the upper model (inspection path evaluation model) is used for quantitative evaluation of the pros and cons of the inspection target point traversal sequence, the lower model (pair path cost calculation model) puts forward the calculation method of the three dimension value of the pair path;Thus, the necessary prerequisite foundation is provided for the subsequent multi-target point inspection path planning.

The invention relates to a sub-pixel positioning method and device for a nuclear radiation detector and the nuclear radiation detector. The method comprises the following steps: in the process of detecting photons by a detector, acquiring a detection signal which is excited by the photons colliding with a detection crystal and is collected by at least one physical pixel; determining signal description data of the corresponding detection signals according to the detection signals of different physical pixels; based on the trained sub-pixel positioning model, according to the signal description data, determining the impact position of the photons in the detector; the impact position is any sub-pixel position relative to the center of the target physical pixel; the target physical pixel is the physical pixel with the strongest detection signal. According to the method, the detection signal excited by the photon impact event is collected, the signal description data is extracted, and the sub-pixel level position information is effectively captured by using the sub-pixel positioning model, so that the accurate sub-pixel impact position of the photon relative to the pixel center with the strongest signal intensity is deduced, and the reliability of sub-pixel positioning is remarkably improved.

The application discloses a current source module capable of simulating output current of an ionization chamber and a nuclear radiation monitoring device, and the current source module comprises an interface unit, a program-controlled switch unit, a V-I conversion unit, a 2N-way DAC, a control unit and a power supply unit which are sequentially connected. The 2N-way DAC outputs multiple voltage signals, then the voltage signals are converted into current signals by the V-I conversion unit, the current signals can enter a preprocessor after the program-controlled switch and the interface, and the control unit can control the size of the voltage signal output by each channel of the DAC and the closing of the program-controlled switch, so that the size of the output current and the control of the direct current or pulse current are realized. The application can simulate the current generated by the ionization chamber in a gamma radiation field, and realizes the detection and result evaluation of the nuclear radiation monitoring device which is composed of the ionization chamber and the preprocessor and cannot be disassembled.

An X-ray scanning system includes: a housing configured to be handheld; an X-ray source for scanning a target; a set of first detectors configured to be mechanically coupled to the housing and to detect resulting X-rays received from the target responsive to scanning the target; a second detector configured to be mechanically coupled to the housing; and a set of processors mechanically coupled to the housing and communicatively linked to the first detector and to the second detector so as to receive first and second signals, respectively, therefrom. The processor(s) are configured to: generate an image of the target based on the first signal; distinguish, in the second signal, a contribution of passive nuclear radiation detected at the second detector; and provide an output corresponding to the contribution of passive nuclear radiation. A related system for identifying a radioactive isotope, along with corresponding methods, are provided.

The invention discloses a passive nucleon level gage and a level output control method and a monitoring system thereof in a nuclear radiation flaw detection period. The level output method comprises the following steps: judging that nuclear radiation flaw detection interference exists in a measurement environment in which the passive nucleon level gage is positioned; executing at least one of the following output guarantee operations: setting an output switch of the passive nucleon level gage to be in a preset guarantee state, wherein the preset guarantee state is a switch-on state or a switch-off state; or the output switch of the passive nucleon level gage is maintained in the on-off state before it is judged that nuclear radiation flaw detection interference exists; or the normal material level value of the passive nucleon level gauge is replaced with the alternative material level value, or the on-off state of an output switch of the passive nucleon level gauge is determined based on the alternative material level value, and the alternative material level value is used for replacing the normal material level value when flaw detection interference is detected. The normal material level value is a material level value generated on the basis of the real-time measurement data in the state that the guarantee operation is not executed. The device realizes material level output guarantee control during nuclear radiation flaw detection.

The present application relates to nuclear radiation detection technical field, provide a kind of nuclear measurement analog quantity transmission method based on feedback compensation circuit, the hardware part used by this method includes ARM chip, digital-analog converter, digital potentiometer, operational amplifier, isolated voltage current converter, isolation chip, A / D conversion chip, the ARM chip is connected with digital-analog converter, digital potentiometer respectively, the ARM chip is connected with A / D conversion chip after isolation chip, the first operational amplifier is connected with digital-analog converter, digital potentiometer, isolated voltage current converter respectively, the output current of isolated voltage current converter is connected with A / D conversion chip through precision resistance, second operational amplifier.The present application method can be promptly revised output current according to the comparison result of output signal and input signal, and the mode of feedback compensation is used to adjust input signal, improves output accuracy.

This invention relates to the field of nuclear radiation detection technology and discloses a two-dimensional array detector for measuring the spatial distribution of neutrons and photons. The detector body includes a detector body comprising a detection unit layer, a light guide layer, and a readout layer. The detection unit layer, light guide layer, and readout layer are vertically stacked sequentially from top to bottom to form a three-layer modular integrated structure. The layers are precisely mechanically aligned and optically coupled without air gaps. The light guide layer is composed of an array of multiple optical fibers. The detection unit layer is composed of an array of multiple detection units, with each detection unit corresponding to one optical fiber. This invention offers advantages such as modularity, high spatial resolution, and real-time signal processing. It can be applied to the measurement of the spatial distribution of neutrons and photons in the field of boron neutron capture therapy, meeting the practical needs of online real-time measurement of the spatial distribution of the neutron-photon mixed radiation field and accurate verification of the treatment irradiation field dose in boron neutron capture therapy.

The invention discloses a channel gain correction method and system for a multi-channel detector, and relates to the technical field of nuclear radiation detection. The method comprises the following steps: collecting original event data by using a multi-channel detector; energy of all channels triggered by the same event is obtained through action time judgment; calculating the total energy value of each event through the energy of each channel to which each event belongs, counting all events, constructing the total energy spectrum of the channel events, setting an energy screening window according to the position of a photoelectric peak in the total energy spectrum, and reserving the events in the energy screening window as an effective event set; performing channel gain coefficient correction by using an iterative algorithm, and monitoring the energy resolution in real time until convergence; and performing channel-level gain compensation on all original event data by using the finally obtained gain coefficient, and outputting and displaying a corrected energy spectrum and a gain distribution diagram. After gain correction, the energy resolution and the position resolution of the detector can be remarkably improved, and the imaging quality and the quantitative accuracy of the system are improved.

The invention discloses a growth method of an organic-inorganic hybrid two-dimensional phenylethylamine lead bromide perovskite single crystal, relates to a growth method of a phenylethylamine lead bromide perovskite single crystal, and aims to solve the technical problems of long growth period and small thickness of the existing two-dimensional phenylethylamine lead bromide single crystal. The method comprises the following steps: 1, obtaining seed crystals; 2, thermodynamically regulating and controlling the solution supersaturation degree by a constant-temperature water bath device; 3, seed crystal growth is dynamically regulated and controlled through a seed crystal rotating-gradient cooling method under the solution rotating condition, the phenylethylamine lead bromide perovskite single crystal is obtained, the length and width of the phenylethylamine lead bromide perovskite single crystal are larger than 2 cm, the thickness of the phenylethylamine lead bromide perovskite single crystal is larger than 2 mm, fast neutron detection and high-energy nuclear particle screening can be met, and the phenylethylamine lead bromide perovskite single crystal is applied to the field of nuclear radiation detectors.

The invention discloses a multi-legged robot radiation source autonomous positioning method based on AI dynamic path optimization, and belongs to the technical field of nuclear radiation monitoring and intelligent robots, and the method comprises the steps: collecting space radiation intensity data, eliminating pseudo sources, calculating a radiation gradient field, and constructing a radiation field in real time; an improved social network search algorithm is adopted to solve a target function of an optimal path, the target function dynamically fuses a path length and a radiation gradient integral, and a path weight coefficient alpha and a radiation weight coefficient beta are adjusted in real time through a Sigmoid function according to environmental complexity; the multi-legged robot conducts gait self-adaptive control according to the optimal path, and the movement speed is adjusted according to the real-time radiation intensity. According to the method, dynamic path optimization, multi-mode perception and pseudo source elimination are fused, the problems of path disjunction, data distortion, pseudo source interference, insufficient dynamic adaptability and the like in the prior art are solved, and an autonomous and credible radiation source positioning solution is provided for nuclear leakage emergency.