993 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 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 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.

A radiation imaging system includes a radiation imaging apparatus and an imaging control apparatus, the radiation imaging apparatus includes a dose detection pixel that detects a dose of radiation irradiated from a radiation source, and the imaging control apparatus controls the radiation imaging apparatus. Before radiation imaging, the imaging control apparatus specifies a position of the dose detection pixel in a region of interest for calculating a dose indicator value of a radiation image, determines a threshold according to the position of the dose detection pixel, and transmits the position of the dose detection pixel and the threshold to the radiation imaging apparatus. The radiation imaging apparatus makes a setting of the position of the dose detection pixel in the region of interest and the threshold transmitted from the imaging control apparatus, and performs imaging based on the setting.

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 relates to the technical field of bone mineral density detection, and discloses a bone mineral density detection method which comprises the following steps: step 1) image acquisition; step 2) image segmentation; 3) reconstructing a three-dimensional surface; 4) reconstructing three-dimensional body distribution; 5) performing calibration calculation; according to the method, the automatic segmentation algorithm, the three-dimensional reconstruction algorithm and the gray density mapping technology based on the Lambert-Beer law are combined, so that the lumbar vertebra bone mineral density is rapidly and accurately detected, and a reliable basis is provided for early diagnosis of osteoporosis; in addition, the method is based on common X-ray images, is low in radiation dose, is lower in equipment cost, is suitable for basic medical institutions and resource-limited regions, and has wide popularization value and application prospect.

The invention relates to the technical field of nuclear emergency decontamination management, and discloses a nuclear emergency decontamination station partition management method and device based on artificial intelligence, and the method comprises the steps: carrying out the three-dimensional laser scanning and data collection of a pollution region, a decontamination region and a clean region of a nuclear emergency decontamination station, and constructing a decontamination station digital twinborn model; according to the digital twin model of the decontamination station, performing multi-dimensional analysis and weight calculation on the polluted area, the decontamination area and the clean area by adopting an analytic hierarchy process to obtain a partition evaluation parameter matrix; inputting the partition evaluation parameter matrix into a deep reinforcement learning network for dynamic optimization calculation to obtain partition management control parameters; and performing decision analysis and threshold judgment on the radiation dose rate data, the pollution range data, the personnel quantity data and the equipment state data according to the partition management control parameters, and generating an emergency disposal control instruction, thereby realizing cooperative linkage of the pollution area, the decontamination area and the clean area, and improving the accuracy and timeliness of emergency disposal.

A dose feedback system provides real-time or near real-time intra-operative radiation dose feedback system to improve and / or ensure that a proper amount of radiation is delivered to a patient by, for example, carriers (e.g., tile carriers). The dose feedback system can be implemented during medical surgeries, operations, procedures, etc. The dose feedback system may allow a medical professional (e.g., surgeon) to more accurately achieve a prescribed radiation of a dosimetric intent or a more detailed dosimetric plan through adjustments to position, dose, quantity, etc. of carriers prior to terminating the medical procedure (e.g., cavity of tumor bed is closed and / or patient is brought out from under anesthesia) at which point adjusting the radiation dose may be difficult or impossible.

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 discloses a TSV-based multi-layer microsystem interconnection module total dose effect simulation modeling method, and relates to the technical field of three-dimensional integrated microsystems, and the method comprises the steps: obtaining geometric parameters and material parameters of a multi-layer three-dimensional microsystem interconnection module, building a finite element model of a microsystem module based on the geometric parameters and the material parameters, and carrying out the simulation modeling of the TSV-based multi-layer microsystem interconnection module total dose effect. Setting boundary conditions and port excitation; scattering parameters under different material conditions in the finite element model are extracted, frequency points are fixed, and a relational expression of the scattering parameters and material parameters is established; an RLC equivalent circuit model is constructed, and an equivalent circuit extraction method is obtained; according to an equivalent circuit extraction method, in combination with a relational expression of scattering parameters and material parameters, establishing a relationship between return loss parameters and equivalent circuit parameters; and establishing a relation model between the radiation dose and the resistance, inductance and capacitance in the equivalent circuit according to the relation between the return loss parameter and the equivalent circuit parameter. According to the invention, a scientific basis is provided for the reliability design of the three-dimensional microsystem in the radiation environment.

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.

Organometallic precursors are described for the formation of high resolution lithography patterning coatings based on metal oxide hydroxide chemistry. The precursor compositions generally comprise ligands readily hydrolysable by water vapor or other OH source composition under modest conditions. The organometallic precursors generally comprise a radiation sensitive organo ligand to tin that can result in a coating that can be effective for high resolution patterning at relatively low radiation doses and is particularly useful for EUV patterning. The precursors compositions are readily processable under commercially suitable conditions. Solution phase processing with in situ hydrolysis or vapor based deposition can be used to form the coatings.

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.

A computer tomography scanner (102) includes a radiation source (112) configured to emit x-ray radiation, a detector array (116) configured to detect x-ray radiation and generate a signal indicative thereof, and a reconstructor (118) configured to reconstruct the signal and generate sequential spares time line perfusion volumetric image data. The computer tomography scanner further includes a processor (132) configured to process the sequential spares time line perfusion volumetric image data using a trained neural network of a perfusion data enhancing module (136) to produce sequential dense time line perfusion volumetric image data.

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.

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 invention relates to the field of nuclear power, in particular to a control method for natural oxidation of a primary loop of a nuclear power plant. The method comprises the following steps: carrying out primary loop dissolved hydrogen control; primary loop nitrogen purging hydrogen removal; and the primary loop is naturally oxidized. The method is suitable for a VVER unit, the activity concentration of the activated corrosion product in a primary loop main system is reduced, deposition of the activated corrosion product on the surface of main equipment is reduced, and therefore the radiation dose field level in the unit maintenance period is reduced, and the irradiation dose of workers in the radioactive environment is reduced.

A radiographic imaging system includes a control apparatus configured to control a radiation generation apparatus, and a radiographic imaging apparatus including a sensor unit configured to detect radiation emitted from the radiation generation apparatus and a communication unit configured to transmit, to the control apparatus, an irradiation stop signal to stop the radiation generation apparatus from emitting radiation based on a dose of the radiation detected by the sensor unit, wherein the communication unit transmits, to the control apparatus, a plurality of control signals as one set, each of the plurality of control signals including the irradiation stop signal, and wherein the control apparatus stops generation of radiation from the radiation generation apparatus based on the plurality of control signals.

The invention belongs to the field of medical robots, and relates to a method, device and equipment for adjusting a DSA ray frame rate and a storage medium, and the method comprises the steps: obtaining a current exposure frame rate of a DSA; acquiring operation parameters of an operator end; and generating an updated DSA exposure frame rate according to the current exposure frame rate and the operation parameters, and sending the updated DSA exposure frame rate to the DSA, so that the DSA performs imaging according to the updated DSA exposure frame rate. The DSA ray frame rate can be adjusted according to the related motion parameters of the interventional instrument, so that the radiation dose received by an operation object, an operator and an assistant is reduced, and damage caused by radiation is relieved.

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 belongs to the technical field of intelligent regulation and management of X-ray equipment, and particularly relates to an X-ray equipment self-adaptive regulation and management system based on multi-modal intelligent analysis, which comprises an X-ray equipment operation data acquisition unit; the preprocessing unit is used for acquiring data; a multi-modal data analysis unit; an intelligent analysis and decision unit; an X-ray equipment intelligent self-adaptive regulation and control unit; an X-ray equipment intelligent management unit; and an equipment user interaction and question feedback unit. According to the invention, automatic regulation and control of parameters of the X-ray equipment can be realized through application of the intelligent self-adaptive regulation and control unit of the X-ray equipment, and the operation efficiency of the equipment is improved; through cooperative application of the multi-modal data analysis unit and the intelligent analysis and decision-making unit, the radiation dose and the equipment energy consumption are reduced; through the intelligent management unit of the X-ray equipment, the state of the X-ray equipment can be monitored in real time, faults are predicted, maintenance suggestions are provided, and the service life of the equipment is prolonged.

The invention discloses a dual-mode precise regulation and control method and device for a proton treatment system, and relates to the technical field of proton treatment, and the device comprises a superconducting cyclotron, a beam transmission module, a treatment head module which comprises a first ionization chamber, a second ionization chamber, a range regulator, a multi-leaf grating and scanning iron, a treatment chair and a control module, the control module is used for receiving and analyzing a treatment plan and controlling the working states of the superconducting cyclotron, the beam transmission module, the treatment head module and the treatment chair in different working modes according to the treatment plan; the working mode comprises a first working mode and a second working mode, and the radiation dose of a proton beam required by the second working mode is far greater than the radiation dose of the proton beam required by the first working mode. The dual-mode precise regulation and control device can support a conventional working mode and also can support a flash therapy working mode, and different working modes can be switched to realize a treatment plan.