793 results about "Radiation dose" patented technology

The invention discloses a sparse finite angle CBCT reconstruction method and system based on residual diffusion and a storage medium, and the method comprises the steps: carrying out the CBCT sparse finite angle scanning of a to-be-detected target, and obtaining sparse projection data; fDK reconstruction is carried out on the sparse projection data to obtain an initial CBCT image; generating a first optimized CBCT image from the initial CBCT image through an image pre-training network; through the first optimized CBCT image and the sparse projection data, using the trained residual diffusion model to determine a residual image of the to-be-detected target; summing the first optimized CBCT image of the to-be-detected target and the residual image of the to-be-detected target to obtain a second optimized CBCT image of the to-be-detected target, and the second optimized CBCT image is a final CBCT reconstruction image. According to the method, the problems of stripe artifacts and low-contrast tissue annihilation under limited angle scanning are solved, the large-view CBCT reconstruction resolution is improved, and the radiation dose is reduced.

The invention provides a radiation field high-precision reconstruction method based on dynamic geometry aggregation, and relates to the technical field of radiation field reconstruction and computational physics crossing. The method comprises the following steps: extracting a corresponding attenuation coefficient as a priori value; generating a Gaussian radiation element at the position of the monitoring point; calculating the radiation intensity of any point in the space; suppressing mutation of attenuation coefficients of adjacent primitives; gathering to a high dose zone or dispersing to a low dose zone; and generating three-dimensional radiation dose rate distribution by adopting a differentiable split rendering pipeline, and calculating the radiation intensity of any query point in real time by outputting a parameterized Gaussian primitive set. Through the dynamic Gaussian primitive aggregation-physical constraint optimization dual-drive reconstruction framework, the radiation field distribution can still be accurately restored under the sparse detector condition, the error is greatly reduced compared with the traditional method, and the calculation efficiency is obviously improved.

The invention discloses a BNCT dose calculation method, which comprises the following steps: S1, constructing a voxel model, initializing one or more particles in a simulation system, and respectively acquiring the initial position, energy and movement direction of each particle; s2, adaptively selecting a Monte Carlo particle tracking algorithm and a flux counting mode based on the region where the particles are located and the energy of the particles; s3, repeating the step S2 until the particles leave the simulation system or are killed when meeting a truncation condition; and S4, cumulatively calculating dose distribution. Through the BNCT dose calculation method, the Monte Carlo particle transport simulation time is greatly shortened, the BNCT dose calculation efficiency is optimized, and the method is suitable for rapid and high-precision radiation dose simulation under a BNCT complex tissue structure.

The invention discloses a 3DGS-based integrated visual angle synthesis and sparse visual angle CT reconstruction method, which comprises the following steps: establishing an internal and external parameter matrix through X-ray scanning parameters, constructing an initial voxel space and an initialized 3DGS radiation field by combining sparse visual angle projection data and based on an ACUI strategy, modeling anisotropic radiation intensity by utilizing a radiation intensity response function, and reconstructing a 3D visual angle CT model. And generating a virtual projection by adopting volume consistency rendering. And the optimized radiation field is converted into a voxel grid, density contribution is applied to carry out voxel space reconstruction, a reconstructed voxel space is obtained, and a new 3DGS radiation field is generated. And re-rendering the virtual visual angle projection based on the new 3DGS radiation field, performing iterative optimization by using a loss function, and outputting a new visual angle synthetic image and a CT reconstruction body until a preset number of iterations is reached. And an efficient process of one-time training and dual output is realized. The efficiency and precision of X-ray imaging are improved, the radiation dose of a patient is reduced, and meanwhile, a higher-quality imaging solution is provided for medical diagnosis.

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 quadruped robot with multimodal capabilities and embodied large-scale models for use in a 5G nuclear power plant, characterized in that it comprises: a control module, a power module, a robot arm module, a power supply module, a sensor module, a heat sink, an audio module and a housing structure, wherein the control module, the power module, the robot arm module, the power supply module, the sensor module, the heat sink and the audio module are mounted on the housing structure, wherein the control module is respectively connected to the individual modules, iethe power module, the robot arm module, the power supply module, the sensor module, the heat sink and the audio module to control and communicate with the robot, wherein the sensor module comprises a depth camera, a laser sensor, a mobile phone recognition device, an infrared sensor, an ultrasonic sensor and a radiation dose chip, wherein the power module consists of a motor and an electronic speed controller and is thus responsible for the movement of the robot, wherein the robot arm module comprises a motor and a robot arm controller as well as an integrated NFC module on the robot arm, and wherein the power supply module comprises a battery, a power supply manager and a power supply display screen, while the audio module provides remote voice interaction.

The invention discloses a multi-section type linear array X-ray source static real-time CT imaging system and an imaging method, and the multi-section type linear array X-ray source static real-time CT imaging system is provided with a scanning device and a ray source control unit; the scanning device is provided with a multi-section X-ray source array and a detector, the transmitting end of the multi-section X-ray source array faces the detector, and the multi-section X-ray source array is connected with the ray source control unit. The multi-section X-ray source array has the advantages that the multi-section X-ray source array can freely adjust the length and the included angle of the whole section, and the multi-section X-ray source array is suitable for a large-size measured object; 2, the multi-section X-ray source array can use fewer X-ray sources to realize the same wide view field, the design is more free, and the expansion is easier; 3, the distribution of ray sources can be relatively dispersed, the crossing of ray paths is less, and the interference of scattered signals can be obviously reduced; and 4, the exposure strategy of the scanning device can be controlled through the radiation source control unit, and the radiation dose utilization rate is optimized.

The invention provides an off-site full-range radiation risk evaluation method and system under a severe accident of a nuclear power plant, and the method comprises the steps: S1, building a radioactive accident risk evaluation basic model architecture, adapting to a model demand, and building a corresponding basic database; s2, constructing radioactive smoke plume characteristics after the accident; s3, calculating accident site space gridding and smoke plume transmission discretization; s4, sampling meteorological conditions, and simulating smoke plume transmission; s5, calculating the radiation dose in the early stage of the grid domain, and carrying out risk assessment; s6, performing risk assessment on the health effect in the early stage of the grid domain; s7, calculating the medium-and-long-term stage radiation dose in the grid domain, and performing dose risk assessment; and S8, performing health effect risk assessment and accident consequence assessment in the medium-and-long-term stage. According to the method, the whole transportation process of the radioactive smoke plume under a serious accident is simulated, loss effects such as dry and wet settlement and radioactive decay of the smoke plume are considered, and the activity of the radionuclide deposited on the ground and retained in the air in the off-site space range is determined.

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 discloses a temperature control method for low-temperature high-NOx-concentration flue gas denitration in the nuclear industry, and relates to the technical field of flue gas denitration control. According to the method, flue gas temperature time sequence distribution, NOx concentration gradient and environment radiation intensity data are integrated through a space-time alignment algorithm, a synchronous data matrix representing a system coupling state is generated, then a temperature and efficiency response curved surface is established, a high-efficiency temperature area and an inactivation risk area are dynamically divided through fuzzy logic control, and an optimal temperature regulation and control threshold value is recognized. The drift effect of quantitative radiation on the surface temperature of the catalyst is analyzed through regression, a quantitative relation model of radiation dose and temperature zone deviation is established, and real-time correction of anti-radiation compensation parameters is achieved. And finally, optimizing the multi-objective cost function by adopting a non-dominated sorting genetic algorithm, and obtaining dynamic balance between the maximum NOx conversion rate and the minimum temperature fluctuation. And multi-parameter coupling control of a temperature field and a radiation field is realized, and the denitration efficiency stability under a low-temperature condition is remarkably improved.

The invention provides a reactor pressure vessel flange sealing surface defect measuring method and a reactor pressure vessel flange sealing surface defect repairing method. The measuring method comprises the following steps: S1, measuring and calculating the minimum diameter and the maximum diameter of an annular band formed in a sealing ring indentation range; and S2, by taking the center of the container flange as a circle center, inspecting the defect, falling into the range of the annular belt between the minimum diameter and the maximum diameter, on the container flange, and measuring and recording the size and the orientation of the defect. According to the method, corresponding recommended repair methods are provided according to repair criteria for defects of different scales, the method can be used for guiding implementation of nuclear power plant RPV sealing surface maintenance, the repair workload is effectively reduced, the radiation dose of personnel is reduced, the operation and maintenance efficiency is improved, safe and stable operation of a nuclear power unit is ensured, and the economic benefit of power station operation is improved.

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 relates to a nuclear facility radiation field model construction method and a dose evaluation system, and the system is configured to establish a three-dimensional space coordinate system, construct a three-dimensional radiation field model based on radiation field data and radiation source data, and correct the radiation field model at the current moment according to the radiation source data, introducing an attenuation coefficient of the three-dimensional nuclear facility on the original three-dimensional scene model to correct the three-dimensional scene model; correcting the radiation field model based on the corrected three-dimensional scene model; calling the three-dimensional scene model and the radiation field model according to an operation path selected by a user; and simulating the space range of each organ of the human body sweeping along with the movement of the human body in the working path in the three-dimensional scene model, obtaining the time of each organ staying on the path of the unit space, and calculating the real-time dose received by the human organ according to the radiation dose rate in the unit space. According to the invention, the change of the radiation field caused by the disassembly and assembly of the nuclear facility can be corrected, and the optimization of radiation protection is realized.

The invention discloses a nuclear power plant secondary side cleanliness evaluation and radiation shielding method. The method comprises the following steps that S1, whole secondary circuit system equipment of a steam generator is washed; s2, full-coverage cleanliness inspection is carried out in the range from a filter screen of the electric main water feeding pump system to the secondary side of the steam generator, and meanwhile, if foreign matter is found, a cleaning tool is used for picking up the foreign matter; s3, evaluating the cleanliness condition, and if the cleanliness is qualified, ending; if the cleanliness is not qualified, returning to the step S1; s4, if the foreign matter falls off after the steam generator runs, stopping the equipment, and filling the secondary side of the steam generator with water to a preset position for reducing the radiation dose; and S5, picking up foreign matters by using a cleaning tool. Full-coverage cleanliness inspection is carried out in the range from the filter screen of the electric main feed pump system to the secondary side of the steam generator, effective verification of the secondary loop foreign matter flushing effect and radiation shielding when necessary are achieved, and foreign matter remaining on the secondary side of the steam generator is avoided.

It is provided a method for generating a plurality of potential treatment plans, each treatment plan specifying a distribution of radiation to a target volume, the method being performed by a treatment planning system and comprising the steps of: generating a plurality of potential treatment plans (12), for performing multi-criteria optimization (MCO), based on a set of optimization functions. At least one optimization function depends on the distribution of the product of radiation dose and linear energy transfer, LET, in a specified region of the patient, yielding a plurality of treatment plans.

The invention discloses a rapid large-scale calculation simulation method and system for gamma radiation dose in a dynamic environment and a storage medium, and belongs to the technical field of ionizing radiation protection. The method comprises the following steps: firstly, constructing a triangular mesh scene model containing a radioactive source and a shielding body, and discretizing the radioactive source into a local point kernel; global coordinates of the point kernel and the vertex of the triangle are calculated in parallel by using a GPU, and a maximum parallelization hierarchical surrounding structure MPBVH of the scene is constructed; ray tracing is executed in parallel on the GPU, and all intersection points of MPBVH calculation rays and the shielding body are traversed to determine the thickness and the material of each shielding layer; and finally, dose values of all counting grids are calculated in parallel by adopting a point kernel method. When a radioactive source or a shielding body in a scene is subjected to dynamic changes such as movement and rotation, geometric data can be quickly updated, and calculation can be executed again. According to the method, the speed of large-scale point kernel calculation is increased, the influence of the environmental complexity on large-scale calculation time consumption is small, and the method can be suitable for rapid large-scale calculation and dynamic updating of the radiation field in the complex dynamic environment.

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 provides a two-dimensional region-of-interest driven three-dimensional image navigation control method and system, and the method comprises the steps: obtaining at least two two-dimensional images collected under different poses, and selecting a region of interest on the two-dimensional images; mapping a region of interest on the two-dimensional image into a three-dimensional imaging space to obtain a first region pose of the region of interest in the three-dimensional imaging space, and calculating a three-dimensional target region including the region of interest according to the first region pose; and controlling the three-dimensional image equipment to move so as to enable the imaging center of the three-dimensional image equipment to coincide with the center of the three-dimensional target area. The accuracy of three-dimensional imaging is improved, the radiation dose borne by a patient is reduced, waste films caused by inaccurate shooting positions are avoided, the operation duration is shortened, the operation efficiency is greatly improved, a doctor only needs to check the interested area on the two-dimensional image, the device can be automatically guided to move to the corresponding position, and the operation efficiency is greatly improved. And the intelligent degree and the reliability of the three-dimensional image equipment are improved to a great extent.

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 relates to the technical field of gamma radiation dose calculation, and particularly discloses a gamma radiation dose calculation method based on a Unity engine, a program, equipment and a storage medium. In order to solve the problems that ray tracing is complex and low in efficiency in complex irregular geometry by means of an existing point kernel integration method, the physical calculation capacity of a Unity engine is introduced, ray tracing is conducted through Physics. Raycast interface iteration, and gamma radiation dose calculation under the multi-layer shielding condition is optimized. The method comprises the following steps: acquiring radioactive source energy, intensity, shielding body density, mass attenuation coefficient and detection point coordinates; constructing a radioactive source model and generating a point kernel set through parallel array ray discretization; performing ray tracing on the point core set to obtain a list of all intersection points of rays and the shielding body; and calculating the shielding thickness of each layer according to the intersection point list, calculating the dose contribution of each point core in combination with the accumulation factor, and summing to obtain a total dose value.

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 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.

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.

A computer-implemented method for determining an estimation of a two-dimensional scattered radiation distribution in a two-dimensional X-ray image that is based on an imaging procedure performed by an X-ray detector is provided. The method includes receiving the X-ray image, applying an estimation algorithm to the X-ray image or to a two-dimensional intermediate image determined from the X-ray image. The estimation algorithm determines a respective two-dimensional partial scattered radiation image for a plurality of physical scatter processes such that image values of pixels of the respective partial scattered radiation image in each case describe an estimated value for a respective scattered radiation dose that was applied to a respective detector region of the X-ray detector assigned to the respective pixel during acquisition of the X-ray image by the respective physical scatter process. The estimation of the scattered radiation distribution is determined based on the plurality of partial scattered radiation images.

The invention discloses an accurate X-ray radiation dose measurement system based on artificial intelligence, which comprises the following steps: acquiring CT image data of a patient and pulse irradiation parameters of radiotherapy equipment through terminal equipment, and calculating a patient specific anatomical structure dynamic influence factor set, a pulse waveform time domain characteristic factor and a tissue interface scattering correction factor; all the parameters are substituted into a dose measurement formula to obtain an accurate X-ray radiation dose value; through a deep fusion image recognition technology (such as a high-resolution anatomical structure, tissue density gradient and heterogeneous region distribution provided by CT / MRI), a secondary particle scattering effect of a junction region of a tumor and a normal tissue can be accurately represented; and dynamic anatomical information (such as respiratory movement and organ displacement) in the image is combined to correct the time characteristic (such as dynamic change under an instantaneous high dose rate) of the pulse radiation field in real time, so that the dose calculation accuracy of a fast algorithm in a complex scene is remarkably improved.

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.

A neural network (such as a transformer neural network) configured to determine radiation doses can be trained using a training corpus that comprises a plurality of different resultant radiation doses (such as, but not limited to, sparsely-written resultant radiation doses) and a plurality of different input items that each correspond to a particular one of the plurality of different resultant radiation doses. Those input items can comprise at least one, two, three, or each of a patient image (such as, but not limited to, computed tomography imagery and / or Digital Imaging and Communications in Medicine-compatible imagery), a fluence map, radiation treatment platform geometry information, and / or target dose volume information (such as, but not limited to, sparsely-read target dose volume information). A radiation dose for a patient can be generated by providing patient image information as input to a trained neural network and outputting a determined radiation dose for the patient.

The invention provides a dynamic PET image and kinetic parameter prediction method and device and a storage medium. The method comprises the steps that first N frames of dynamic PET image data are obtained and preprocessed to obtain a standard image sequence; and inputting the standard image sequence into the prediction model to obtain subsequent frame dynamic PET image data and a corresponding kinetic parameter map. The prediction model comprises an image structure sensing channel for extracting image structure features, a dynamic modeling channel for extracting dynamic parameter features, a cross fusion module for fusing the image structure features and the dynamic parameter features, and a prediction reconstruction module for performing prediction reconstruction based on a fusion result. The method has the advantages that image structure features and kinetic parameter features can be fused on the basis of the dynamic PET image early-stage frames, scanning time and radiation dose are reduced, and meanwhile follow-up frame dynamic PET image data with high image quality and dynamic interpretability and the corresponding kinetic parameter atlas are generated.

The invention relates to the field of post-accident gamma dose rate measurement, and provides a post-accident gamma dose rate dynamic measurement method and system based on multi-detector fusion, and the method comprises the steps: obtaining original signal data and environment parameter data; processing the original signal data, the environmental parameter data, the accumulated radiation dose and the displacement damage energy by adopting a deep learning network to obtain corrected signal data; processing the correction signal data and the environmental parameter data through a time sequence prediction network to obtain a dynamic weight distribution result of each detector; processing the correction signal data and the dynamic weight distribution result based on a self-calibration confidence evaluation network to obtain a confidence evaluation result; and processing the correction signal data, the dynamic weight distribution result and the confidence evaluation result through a weighted fusion algorithm to obtain a dynamic measurement result of the gamma dose rate after the accident. According to the invention, high-precision dynamic measurement, real-time damage compensation and nuclear safety level reliability evaluation of the gamma dose rate after an accident are realized.