693results 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 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 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.

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 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 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.

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.

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 invention discloses a full center dose verification method based on a no-wash film EBT3, and belongs to the technical field of radiation measurement, and the method specifically comprises the following steps: continuously collecting an irradiated radiation chromatography film, and synchronously obtaining gray data and a scanning device driving voltage sequence; establishing a response function model between the driving voltage and the gray response according to the driving voltage value at each acquisition moment and the mean value of the corresponding gray data; determining a target voltage in advance, determining a correction coefficient corresponding to each driving voltage value based on the target voltage and the response function model, correcting a preset dose-gray curve graph according to the correction coefficient, obtaining the gray data of the current film and the corresponding driving voltage, and correcting the gray value point by point by using the correction coefficient, and based on the corrected dose-gray curve, converting into a dose value, and finally generating a dose distribution diagram. According to the invention, through real-time monitoring and dynamic correction of scanning voltage fluctuation, the accuracy of dose measurement is significantly improved.

The invention provides a radiation detection device and method for measuring ultra-wide-range gamma rays, and relates to the technical field of radiation detection.The radiation detection device comprises a detection assembly, a radiation shielding assembly and a signal processing assembly, and the signal processing assembly is located in the radiation shielding assembly; the detection assembly comprises three GM counting tubes with different measuring ranges and an acquisition circuit, and the acquisition circuit is used for converting signals output by the GM counting tubes into voltage counting signals; the signal processing assembly comprises a high-voltage control circuit, a power supply processing circuit, a pre-amplification circuit and a processor, the power supply processing circuit is used for converting a direct-current power supply signal and then transmitting the converted direct-current power supply signal to the high-voltage control circuit and the acquisition circuit, and the high-voltage control circuit is used for outputting a high-voltage power supply signal to each GM counting tube; the pre-amplification circuit is used for filtering and amplifying the voltage counting signals, and the processor is used for determining a target radiation dose rate according to the processed voltage signals. The radiation detection device provided by the invention has a relatively wide measuring range and relatively high measurement precision.

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 provides a radioactive biological experimental facility radiation environment monitoring and personal dose monitoring method, which comprises a fixed radiation dose monitor, a portable radiation dose monitor, a personal dose instrument, an experimental facility computer system docking port, an analysis center and an early warning judgment module, the experimental facility environment radiation dose can be monitored in real time, single-time operation personal cumulative doses under three different conditions can be obtained through an experimental facility computer system, radiation dose summary analysis can be carried out on radioactive sources operated in the experimental facility, radiation dose changes under different radioactive source operations are obtained, and the experimental facility environment radiation dose monitoring system can be used for monitoring the experimental facility environment radiation dose in real time. And finally, performing early warning according to the environmental radiation dose and the individual accumulated dose result. The environment radiation state can be monitored timely, accurately and effectively, and the external irradiation dose of personnel can be monitored and evaluated in real time.

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 present invention provides apparatuses comprising a plurality of junctions providing a Seebeck effect, configured as alternating hot and cold junctions. The apparatus can be configured such that the cold junctions exhibit a different thermal behavior than the hot junctions in response to incident radiation. The junctions can be connected in series, such that the sum of the Seebeck effect from the plurality of junctions provides a sensitive, inherently calibrated indication of heating of the apparatus responsive to incident radiation, and therefore of the radiation itself.

The invention provides a wireless electronic personal dosimeter capable of dynamically adjusting an alarm threshold value and a control method, and relates to the technical field of radiation monitoring. Comprising a detection module used for collecting historical dose data of a user and constructing a personal dose management library. And the wireless communication module is used for extracting accumulated dose data. And the man-machine interaction module is used for setting a fixed alarm threshold value, setting a personalized alarm threshold value according to the real-time accumulated dose and the accumulated dose data, comparing the fixed alarm threshold value with the personalized alarm threshold value in real time, and selecting a lower value as a real-time alarm triggering standard. And the alarming and updating module is used for judging whether the current dose of the user exceeds a real-time alarming triggering standard, if so, alarming, and uploading the current dose to the personal dose management library for updating. According to the invention, through setting the personalized alarm threshold value, the personal dose accumulation risk can be effectively reduced, the personnel in a low-dose environment for a long time can be more effectively protected, and personalized and precise management of radiation protection is realized.

The invention discloses a real-time processing method for a data missing value of a regional radiation monitor, and relates to the technical field of data processing, and the method comprises the steps: obtaining indoor radiation sequence data and outdoor radiation sequence data generated in the operation process of the regional radiation monitor in a historical time period; determining a medicine injection moment based on fluctuation characteristics of the intragate radiation sequence data; based on the time corresponding relation among the medicine injection time, the indoor radiation sequence data and the outdoor radiation sequence data, the outdoor performance time is determined, multiple suspected outdoor performance time before the current time are compared with the outdoor performance time in the historical time period, and the true probability of the suspected outdoor performance time is obtained; based on the true probability, the radiation fluctuation integrity degree of the in-gate radiation sequence data processed through a linear interpolation method is judged; and generating a required data compensation measure based on the radiation fluctuation integrity degree. The technical effect of improving the judgment accuracy of the abnormal radiation event is achieved.

The invention relates to the technical field of radiation environment monitoring, and discloses a dose calculation method and system based on radiation environment monitoring data. The method comprises the following steps: acquiring radiation source data, calculating initial radiation field distribution based on the data, obtaining an initial dose deposition value of each space point in a monitoring area, analyzing interaction among particles, and determining an energy redistribution coefficient of each space point; adjusting the initial dose deposition value point by point by using the coefficient to obtain corrected three-dimensional dose concentration field data, calculating a gradient vector between spatial points, and generating an optimized gradient distribution diagram; extracting a boundary point set with gradient change exceeding a threshold value, constructing a contour surface grid to form a three-dimensional contour surface structure, obtaining a time sequence radiation source data iteration updating coefficient, and obtaining a concentration field time sequence evolution sequence; the high-concentration area is identified and marked based on the sequence, the high-concentration area and the three-dimensional contour surface structure are fused, a visual distribution model reflecting the dose concentration is generated, and the accuracy of radiation dose calculation is improved.

A radiation monitoring system for a nuclear power plant, comprising: a radiation monitoring device (110); a central control platform (120) which is communicatively connected to the radiation monitoring device (110), wherein a data acquisition module (121), an analysis and determination module (122), and a warning and alert module (123) are provided in the central control platform (120); and a smart display terminal (130), which is communicatively connected to the central control platform (120). The data acquisition module (121) acquires monitoring information and parses same to generate parsed information; the analysis and determination module (122) performs statistical analysis processing on the parsed information to generate statistical analysis data, and generates an alert instruction when the statistical analysis data falls within a preset range; the warning and alert module (123) performs alert processing on the basis of the alert instruction and generates warning information; the smart display terminal (130) displays the warning information, and generates scheduled analysis reports on the basis of the statistical analysis data. Real-time monitoring of radiation of nuclear power plants is achieved.

The invention discloses an aviation radiation dose global distribution real-time calculation system based on ground detection equipment, which belongs to the technical field of radiation detection and comprises a ground radiation detection module, a dose simulation module and a data correction module. The ground radiation detection module is used for continuously collecting ionizing radiation data of an atmospheric bottom layer in a calm state and a solar high-energy particle event so as to improve data precision and a signal-to-noise ratio under a weak dose, and the dose simulation module receives latitude and longitude, height and time parameters of an aviation flight path, and calculates a standard atmospheric model and a cosmic ray energy spectrum in combination with the standard atmospheric model and the cosmic ray energy spectrum. The data processing module is used for calculating theoretical dose rates and particle type distribution of different height levels based on a Monte Carlo method and outputting the theoretical dose rates and the particle type distribution, and the data correction module is used for dynamically correcting parameters and weights of simulation results by combining measured data based on a deep learning algorithm of deep learning, so that adaptive fusion of the simulation data and the measured data is realized; and the ground radiation detection module comprises a semiconductor radiation detector, a data acquisition and preprocessing unit, a remote control module and a network communication module. The system has the characteristics of high real-time performance and wide coverage range.

The present disclosure provides a calibration device for a super high dose rate radiation device comprising a plurality of beam modules for emitting a plurality of radiation beamlets, the calibration device comprising: a calibration target assembly comprising a target portion, wherein the target portion is located at a predetermined radiation region of the super high dose rate radiation device during a calibration process; wherein the target portion is used as a reference to calibrate a convergence deviation of the plurality of radiation beamlets converging at the predetermined radiation region. A calibration method and a super high dose rate radiation device are also provided.

The invention provides a proton dose distribution determination method and device based on a graphics processor, which can be applied to the technical field of medical radiation dose calculation. The method comprises the following steps: calculating pencil beam tracks of a plurality of pencil beams; obtaining respective dose nuclear parameters of the pencil beam at a plurality of intersection points; according to the radiation field dose truncation radius, voxels of interest are determined from tissue voxels in the tissue voxel grid, and the radiation field dose truncation radius represents the upper limit value of the acting distance of all pencil beams in one radiation field to generate remarkable contribution to dose distribution in the transverse direction; calling a plurality of threads to execute dose calculation tasks of the plurality of voxels of interest in parallel based on the respective dose kernel parameters of the plurality of intersection points to obtain voxel deposition doses of the voxels of interest; and determining a dose distribution result related to the specified tissue according to the voxel deposition doses of the plurality of voxels of interest.

The invention relates to the technical field of quality control detection, in particular to a radiotherapy radiation amount detection device and method based on multi-sensor fusion, and the device comprises a data obtaining module which obtains the state information of the connection between a functional plug-in and a detection base, and a data processing module which obtains the state information of the connection between the functional plug-in and the detection base and obtains the state information of the connection between the functional plug-in and the detection base, determining first space attitude information of each functional plug-in relative to the detection base; the global space attitude determination module is used for determining global space attitude information of each functional plug-in in a radiotherapy coordinate system based on the first space attitude information and second space attitude information of the detection base; the multi-dimensional radiation data detection module is used for synchronously acquiring multi-dimensional radiation detection data from each functional plug-in based on global space attitude information in the process of executing radiotherapy irradiation; according to the invention, through combined sensing formed by the micro displacement sensor and the inertial measurement unit, real-time accurate measurement and dynamic compensation of the spatial attitude of each functional plug-in are realized.