965results about "Dosimeters" 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 discloses a radioactive substance multi-point synchronous detection and identification method and system, and relates to the technical field of radioactive substance monitoring. Comprising the following steps: step 1, collecting multi-point radiation data in real time, and preprocessing and storing the data; step 2, constructing a spatial adjacency matrix, estimating a local spatial gradient, calculating an anomaly degree value, taking optimization measures, and performing collaborative anomaly evaluation on the monitoring nodes; 3, calculating a total fitting error value, reversely deducing a leakage source position and leakage intensity in real time, and taking corresponding measures in real time; 4, abnormal trend identification is carried out, an early warning judgment value is calculated, and graded early warning and multi-node cross confirmation measures are implemented; and 5, receiving and storing various types of data, carrying out visualized analysis on the data, and supporting event processing and feedback. The problems that due to the fact that some devices are good in shielding and have physical obstruction, trace leakage is difficult to detect by a single-point monitor, and the risk of long-term retention pollution exists are solved.

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 discloses a nuclear power plant radiation environment monitoring method and system, and the method comprises the steps: collecting the real-time monitoring data of a nuclear power plant radiation environment, and obtaining an environment monitoring real-time data set; performing dynamic threshold comparison on the environment monitoring real-time data set to generate an abnormal identifier or a normal feature vector; under the condition that the abnormal identifier is not generated, inputting the normal feature vector into a pre-trained environment trend prediction model, and outputting a radiation environment change trend curve and a potential abnormal probability in a future preset time period; and based on the change trend curve and the potential abnormal probability, generating graded early warning information, and finally outputting a monitoring early warning result including an early warning grade, prediction time efficiency and a coping strategy. According to the embodiment of the invention, the method can achieve the intelligent monitoring of the whole process of the radiation environment from the abnormal recognition to the prediction intervention, and improves the early warning accuracy, timeliness and decision support capability.

The invention provides a microdosimetry-based evaluation method for a targeted alpha radionuclide treatment biological effective dose, and the method comprises the steps: carrying out the integration of a time activity curve of alpha radionuclide in an organ, obtaining the cumulative activity, and calculating the physical absorbed dose and dose rate of the organ through Monte Carlo simulation; based on micro-dose Monte Carlo simulation, constructing a micro-dose spectrum of the alpha radionuclide to obtain saturation correction dose average linear energy for representing radiation quality; obtaining biological effect parameters of the alpha radionuclide by fitting saturation correction dose average line energy and cell experiment data by using a micro-dose kinetic model; and evaluating the biological effective dose of the target organ in combination with the physical absorbed dose, the dose rate and the biological effect parameter. According to the method, the problem that a biological effective dose evaluation method is lacked in dose evaluation of targeted alpha radionuclide treatment is solved.

The invention provides an irradiation prediction method for irradiated goods, and the method comprises the steps: optimizing irradiation parameters according to an irradiation uniformity evaluation result, including adjusting irradiation time, irradiation intensity and an irradiation mode, and obtaining an optimal irradiation parameter combination through an iterative optimization method; according to the optimized irradiation parameters, an irradiation scheme including irradiation time, irradiation intensity and an irradiation mode is made, the irradiation scheme is input into an irradiation equipment control system, and the irradiation process is automatically executed; and carrying out sampling detection on the goods after actual irradiation, measuring irradiation doses at different positions in the goods, evaluating an actual irradiation effect, verifying the accuracy of a simulation model and optimization parameters, and correcting the simulation model and an optimization algorithm according to a verification result.

Disclosed is a method for spectrally unmixing spectral data originating from a set of spectral sources and including a series of one or more optical spectra. The method can include modeling the spectral data using an endmember matrix and an abundance matrix, the endmember matrix including a set of endmember spectra respectively corresponding to the set of spectral sources, and the abundance matrix indicates an abundance of each endmember spectrum in each spectrum. The method can also include providing external prior spectral information comprising prior endmember information and prior abundance information conveying at least partial prior knowledge about the endmember matrix and the abundance matrix, respectively, and performing a spectral unmixing operation on the spectral data to determine a solution for the endmember and abundance matrices, using the external prior spectral information as input. The method can be employed for calibrating spectral detection systems such as scintillator-based fiber dosimeters.

The invention discloses a method and a system for determining optimal parameters of an X-ray excited extra-high voltage composite apparatus, and relates to the technical field of extra-high voltage electrical equipment detection. The method comprises the following steps: remotely operating the X-ray machine and calculating partial discharge intensity; for the current irradiation position, the tube voltage and the tube current are gradually adjusted, parameters are dynamically optimized based on the quantitative relation between the partial discharge intensity and the radiation dose rate change rate, and the optimal parameters are recorded; and changing position repetition parameter optimization, and constructing a BP neural network model after data set training optimization so as to predict an optimal irradiation position. The optimized BP neural network adopts an improved sparrow search algorithm to optimize an initial weight and a threshold value, and combines Bayesian to optimize a learning rate and a hidden node number. Accurate optimization of excitation parameters and irradiation positions is achieved, detection accuracy and safety are both considered, the optimal irradiation position positioning efficiency is improved, and the method is suitable for ultra-high voltage GIS detection of different voltage grades.

A hospital proton zone radiation protection performance intelligent monitoring and evaluation method and device relate to the radiation monitoring field, and the method comprises the following steps: carrying out three-dimensional scanning on an actual building structure and an actual device layout of a target proton treatment center to obtain three-dimensional scanning data, and correcting a preset BIM model by using the three-dimensional scanning data to obtain a three-dimensional building model; after the detection equipment is started, obtaining a measured dose rate level of the target proton treatment center at a preset target measurement point; and performing curve fitting on the measured dose rate level to obtain a measured dose rate curve, fusing the simulated dose rate level and the measured dose rate curve to obtain an actual dose rate level of each building structure position, and mapping the actual dose rate level into a three-dimensional building model to obtain a three-dimensional dose distribution diagram. By implementing the method, the radiation protection level of the proton treatment area of the hospital can be displayed more visually.

The invention discloses a three-dimensional radiation field construction method and system, and the method comprises the steps: firstly obtaining an actual three-dimensional coordinate parameter set and an actual radiation dose rate parameter set of a to-be-measured scene, constructing a standard covariance matrix according to the parameters, selecting a to-be-predicted point, generating an actual covariance vector for the to-be-predicted point, and carrying out the calculation of the actual covariance vector. Generating predicted radiation dose rate parameters based on the standard covariance matrix and the actual covariance vector, and collecting the predicted radiation dose rate parameters of the plurality of points to be predicted into a predicted radiation dose rate parameter set, and finally, generating a three-dimensional radiation field according to the actual three-dimensional coordinate parameter set, the actual radiation dose rate parameter set and the predicted radiation dose rate parameter set. According to the method, the correlation between the trajectory points is represented through the covariance, and the conversion relation between the to-be-predicted point and each trajectory point is established through the conversion relation between the actual covariance vector and the standard covariance matrix, so that the radiation dose rate of the predicted point is calculated, the radiation dose rate of more point positions is obtained, and the precision of the three-dimensional radiation field is improved.

The embodiment of the invention particularly relates to a dosage monitoring device based on a scintillation fiber array and a beam control device. In the dose monitoring device, when a beam passes through a two-dimensional scintillation optical fiber array detector, a plurality of first scintillation optical fibers arranged in parallel in a first scintillation optical fiber layer and a plurality of second scintillation optical fibers arranged in parallel in a second scintillation optical fiber layer are excited to emit scintillation fluorescence, and the scintillation fluorescence is transmitted along the optical fibers and received by a photoelectric detection unit; and the photocurrent signal is further converted into a voltage pulse signal by the current-voltage conversion unit, and the output dose information and the radiation field dose distribution information of the electron accelerator can be further obtained according to the voltage pulse signal.

The invention provides a signal processing method for radioactivity detection equipment and the radioactivity detection equipment, and the signal processing method for the radioactivity detection equipment comprises the steps: analyzing a collected nuclear pulse signal, and obtaining pulse amplitude information; performing spectrum stabilization according to the pulse amplitude information to obtain a spectrum-stabilized energy spectrum; and determining a nuclide identification result and a dose rate calculation result based on the spectrum-stabilized energy spectrum. According to the technical scheme, on one hand, the current environment dose rate level can be determined, it is ensured that the radiation dose received by workers is within the safety limit value, and therefore the radiation risk can be reduced, and the health and safety of the workers are guaranteed; and on the other hand, specific radionuclides can be identified, so that the pollution source can be determined.

The invention provides a dose distribution determination method and device based on a graphics processor, and electronic equipment, which can be applied to the technical field of medical radiation dose calculation. The method comprises the following steps: based on radiography data of a target object, simulating sampling data of action of each tissue of a organism and particles, and constructing a digital phantom; based on the configuration parameters, the accelerator head model is used for processing a primary particle beam determined based on the simulation particle source to generate a target particle beam, the shape of the target particle beam is matched with the shape of the tumor tissue of the target object, and the configuration parameters comprise the upper limit parameter of the photon reaction action times; processing the target particle beam and the digital phantom by using a physical action model to obtain a particle deposition energy distribution result generated when the target particle beam is conveyed to the digital phantom; and obtaining a dose distribution result according to the particle deposition energy distribution result and the energy dose conversion factor.

The present disclosure provides a calibration device for an ultrahigh dose rate radiation device, the ultrahigh dose rate radiation device comprising a plurality of beam modules for emitting a plurality of radiation beams, the calibration device comprising: a calibration target assembly comprising a target portion, the target part is located in a preset radiation area of the ultrahigh dose rate radiation device in the calibration process; wherein the target part is used as a reference to calibrate the intersection deviation of the plurality of radiation beams in the predetermined radiation area. The invention also provides a calibration method and an ultrahigh dose rate radiation device.

The invention relates to the technical field of luminescent materials, in particular to a zero-dimensional organic-inorganic manganese-based halide scintillating material and a preparation method and application thereof.The preparation method comprises the following steps that manganese bromide and diisopropyl ammonium bromide are mixed and then dissolved in a mixed solvent, heating and stirring are conducted, and a precursor solution is obtained; heating after filtering, preserving heat at 60-100 DEG C, and crystallizing to separate out yellow crystals; and washing the yellow crystal with isopropanol, carrying out suction filtration, and drying to obtain the zero-dimensional organic-inorganic manganese-based halide scintillating material. According to the zero-dimensional organic-inorganic manganese-based halide scintillation material and the preparation method and application thereof, the obtained scintillation material emits bright green light under X-ray excitation, the detection limit is far lower than the standard dosage of X-ray diagnosis, and the zero-dimensional organic-inorganic manganese-based halide scintillation material has wide application prospects in the fields of high-energy physics, security inspection, medical detection and the like.

The invention provides an electron irradiation dose on-line measurement and feedback calibration system and method, and relates to the technical field of automation control, and the system comprises a processing module which is used for converting an original dose signal into a five-path digital reading sequence, carrying out the timestamp alignment and space coordinate calibration of the five-path digital reading sequence, and outputting a calibration result; generating a three-dimensional discrete coordinate data set representing radiation field intensity space distribution; and the extraction module is used for identifying a radiation intensity global maximum value point from the three-dimensional discrete coordinate data set as a spatial registration origin, extracting two feature straight lines representing a radiation scattering dominant direction, and calculating a spatial orientation included angle between the two feature straight lines to determine a radiation scattering main influence area. According to the invention, precise processing of an original dose signal, scientific positioning of a radiation influence area and construction of a dynamic compensation model are realized through cooperation of multiple modules, a high-confidence dose value can be output, feedback calibration is completed based on a time sequence drift trend, and the precision and reliability of on-line measurement of the electron radiation dose are effectively guaranteed.

The invention relates to the technical field of radiation dose monitoring, in particular to a radiation dose monitoring method, device and system, and the method comprises the steps: obtaining the radiation dose data of a flaw detection room, and the temperature and humidity data in the environment; obtaining an influence coefficient of a linear fluctuation degree of radiation dose data caused by environment temperature change and humidity change, and further obtaining an influence coefficient of radiation dose monitoring caused by environment temperature and humidity change; the radiation dose irregular fluctuation change degree caused by equipment operation is calculated, the influence coefficient of the start-stop frequency and the time interval of the equipment is obtained, and the comprehensive influence significance value of the radiation dose monitoring by the environment change and the equipment operation state is obtained by combining the dispersion degree of all radiation dose data. And adjusting the step length factor in the radiation dose monitoring data filtering process to obtain a radiation dose monitoring result. According to the invention, the radiation dose data monitoring precision can be improved.

The invention discloses a personal dosimeter capable of nuclide identification, and the dosimeter comprises a scintillation detector which is composed of a scintillation crystal and SiPM and captures an energy spectrum signal of a ray; the signal amplifier receives the voltage signal output by the SiPM and preprocesses and amplifies the voltage signal; the multichannel analyzer is used for receiving the amplified signal output by the signal amplifier and realizing energy spectrum acquisition in a target energy range; and the MCU receives the signals acquired by the multichannel analyzer and performs energy spectrum analysis. According to the invention, the scintillation detector based on SiPM and scintillation crystals is used, so that the small size and high sensitivity of the personal dosimeter are realized; according to the multi-channel analyzer, the multi-channel analyzer capable of setting the energy range is realized through the ADC and the comparator, and the design of a peripheral circuit is extremely simplified; the simplified nuclide identification method is designed based on prior information, the range of a nuclide library is narrowed, and the requirements of nuclide identification in a specified application scene for the computing power of a system and the complexity of an analog circuit are further reduced.

The invention discloses a Monte Carlo rapid dose calculation method. The method comprises the following steps: loading simulation parameters; obtaining particle source phase space data of the radiotherapy accelerator; obtaining human body anatomical structure image data, and reconstructing a human body three-dimensional matrix; gridding the three-dimensional human body matrix; inputting Monte Carlo dose calculation parameters, and constructing a refined Monte Carlo dose calculation physical model; according to the method, the input data is dynamically compressed by utilizing the structured sparse characteristic of the NVIDIA video card, so that the effective utilization rate of the video memory is improved, and the continuous operation of a calculation task is ensured; the MIG instance management technology is combined with multi-dimensional scheduling and cross-instance collaboration, so that the GPU resource utilization rate is improved, and the advantages are obvious especially in a multi-task parallel scene. The GPU Monte Carlo computing system and the GPU Monte Carlo computing method work cooperatively, the hardware performance of the NVIDIA Amperee and the hardware performance of a graphics card of a next generation of architecture are brought into full play, the Monte Carlo dose computing efficiency is improved to a new level, the computing time is shortened, and the GPU Monte Carlo computing requirement of particle transport is powerfully supported.

The embodiment of the invention provides an assessment method and device for nuclear power off-site radioactive substance release influence, and belongs to the technical field of nuclear power. The method comprises the following steps: acquiring an evaluation range for evaluating the release influence of radioactive substances, wherein the radioactive substances are released in a smoke plume form; within a preset evaluation duration, simulating the generation and movement process of the smoke plume within the evaluation range according to the meteorological condition of the release site, and obtaining the accumulated concentration and settlement concentration of the smoke plume; calculating according to the accumulated concentration and the settlement concentration to obtain the dose of air immersion external irradiation, the dose of surface external irradiation and the dose of suction internal irradiation in the evaluation range; and performing radiation evaluation according to the dose of the air immersion external irradiation, the dose of the surface external irradiation and the dose of the suction internal irradiation to obtain an evaluation result. According to the embodiment of the invention, migration, settlement, diffusion and other phenomena of the radioactive smoke plume in different areas outside the field can be tracked, influences of meteorological condition changes and settlement are coupled, and the accuracy of an evaluation result is improved.

The invention relates to an object X-ray device (10) comprising a radiation source (12) configured to generate and emit electromagnetic radiation for irradiating an object, and a detector device (16) arranged such that the emitted electromagnetic radiation, which at least partially passes through the object, is at least partially reflected by the detector device, and configured to generate an X-ray image of the object. In addition to the detector device (16), a sensor arrangement (20) is provided, which is configured to determine a radiation characteristic associated with the radiation source (12).An evaluation unit (26) is designed to determine or receive a quality parameter of the acquired radiographic image, to evaluate the radiation characteristic and to make a statement about the condition of the detector device and / or the radiation source based on the quality parameter and the radiation characteristic.

A method for processing data relating to a radiological examination of a patient by way of a determining device, comprises the steps of acquiring doses (Ci, ti) measured at a plurality of times ti, storing these time-stamped measurements of radiation doses, and acquiring at least one DICOM digital file containing information on the examination, wherein the method comprises the following steps: acquiring and storing at least one DICOM digital file delivered by the tomograph during or after a tomography; acquiring and storing time-stamped measurements of the doses detected via a scintillating fiber placed on the table, and time-stamped movements of the table; interpolating the measurements (Ci, ti) with data of the image (DICOM) in a common interpolated space and constructing a table (Ck, DICOMk) in the interpolated space; and determining a table of the average dose levels Tz in each slice T depending on the data (DICOMk, Ck).

The invention relates to a method for evaluating the radiation dose of special public nearby a nuclear facility, and the method comprises the steps: estimating the concentration distribution of radionuclides in air, surface soil and a biological medium nearby the nuclear facility through collecting the radiation dose evaluation parameters of a target special public and combining an environment quality evaluation model; based on the data, the annual effective dose of the target special public at the nuclear facility boundary and the living quarter is calculated, and a plurality of ways such as inhalation internal irradiation, air immersion external irradiation, surface deposition external irradiation and ingestion internal irradiation are considered. In addition, a dynamic calculation method is also introduced, especially for the influence of year-by-year change of the cumulant of radionuclides deposited on the earth surface, factors such as decay, resuspension and infiltration into underground water of nuclides are fully considered, and the accuracy and foresight of evaluation are improved. Accurate and comprehensive technical support is provided for radiation protection of the special public around the nuclear facility, and the requirements of the nuclear facility public for dose monitoring and risk management are met.

The embodiment of the invention particularly relates to a beam parameter monitoring device and a beam control device of an electron accelerator. In the monitoring device, a beam output by an electron accelerator sequentially passes through a first annular channel and a second annular channel, and a processor is connected with a first cylindrical electrode, a second cylindrical electrode, a third cylindrical electrode, a fourth cylindrical electrode, a fifth cylindrical electrode, a sixth cylindrical electrode, a seventh cylindrical electrode and an eighth cylindrical electrode. Induced currents respectively corresponding to a first cylindrical electrode, a second cylindrical electrode, a third cylindrical electrode, a fourth cylindrical electrode, a fifth cylindrical electrode, a sixth cylindrical electrode, a seventh cylindrical electrode and an eighth cylindrical electrode when a beam output by an electron accelerator continuously passes through a first annular channel and a second annular channel in sequence are monitored; and obtaining output dose information and radiation field dose distribution information corresponding to the output beam of the electron accelerator. And output dose information and radiation field dose distribution information corresponding to the output beam of the electron accelerator can be accurately monitored.

Disclosed are a radiation protection robot and a scattered inspection apparatus. The radiation protection robot includes: a first wheel capable of allowing the radiation protection robot to move; a shielding device capable of reflecting and / or absorbing radiation; and a radiation sensor for sensing radiation. The radiation protection robot is configured to move through the first wheel towards an area where the radiation dose value sensed by the radiation sensor is increased, and shield the propagation of radiation through the shielding device.

To provide techniques capable of shorting the time required for calibration.SOLUTION: An embodiment comprises: determining an effective voltage value V1 of a high kV on the basis of energy information of X-rays detected in a first sub-region of a detector assembly and energy information of X-rays detected in a second sub-region of the detector assembly, when the high kV is applied to an X-ray tube; determining an effective voltage value V2 of a low kV on the basis of energy information of X-rays detected in the first sub-region of the detector assembly and energy information of X-rays detected in the second sub-region of the detector assembly, when the low kV is applied to the X-ray tube; calculating a correction coefficient required to correct beam hardening on the basis of the effective voltage value V1; and calculating a correction coefficient required to correct beam hardening on the basis of an effective voltage value V2.SELECTED DRAWING: Figure 15

The invention provides a radiation dose evaluation method and system based on radiation environment monitoring data, and relates to the technical field of radiation environment monitoring. The method comprises the following steps: recording the release source intensity of each nuclide at a release point, drawing an equally-spaced concentric arc grid, calculating the release height by combining the ground and the release point air pressure, air density and gravitational acceleration, and assigning nuclide hazard factors to the outer edge of the grid; according to the distance between the release point and the outer edge of the grid, diffusion parameters are calculated by using an empirical formula, a Gaussian atmospheric diffusion model is constructed in combination with the release height and hazard factors, and nuclide air activity concentration is output; comparing the total effective dose with a preset threshold value to calibrate a diffusion range, quantifying the radiation dose per unit area, and dividing atmospheric stability coefficient grades; constructing three types of correction factors of release height, material state and weather condition, establishing a comprehensive dose evaluation formula by combining the unit area radiation dose and the correction factors, comparing a preset threshold value, judging a risk level, and performing periodic updating.

The invention relates to the technical field of boron neutron capture therapy, in particular to a dose verification device for boron neutron capture therapy. The objective of the invention is to solve the technical problem that dose distribution of tumor tissues and surrounding thereof cannot be accurately measured. To this end, the dose verification device of the present application comprises: a box; the die body assemblies move in the incident direction of the neutron beam and are arranged in a stacked mode; the die body insertion plate comprises a tumor tissue simulation positioning area containing boron-10 with a first concentration and / or a normal tissue simulation positioning area containing boron-10 with a second concentration, and the first concentration is greater than the second concentration; the dose detection module is used for detecting distribution data of secondary particles generated after the boron-10 and neutrons are subjected to nuclear reaction; and the data processing module is used for acquiring the distribution data and determining the dose distribution in the die body assembly according to the distribution data. According to the application, the difference of the boron-10 concentration of the tumor tissue and the normal tissue can be better simulated, and the dose distribution of the tumor tissue and the surrounding thereof can be more accurately measured.

The utility model relates to the field of radiation gradient detection technology, and in particular to an electron accelerator ladder bracket, including: a cross-shaped bracket, a plurality of gradient plates, an identification ring and a clamping structure. The utility model, by setting a cross-shaped bracket, makes it easy to place it in the center of a tray, and a plurality of gradient plates are fixedly connected to the cross-shaped bracket at equal intervals in the first extension direction, and the plurality of gradient plates are gradually raised from front to back, so that each gradient plate has a dose sheet installation position and forms a distance gradient. After the dose sheet and the gradient plate are installed using the clamping structure, the electron accelerator height dose distribution measurement can be performed. The use of this device can simplify the distribution position design of the dose sheet and the installation operation of the dose sheet, thereby making the electron accelerator height dose distribution measurement easy to operate.