186 results about "Dose rate" patented technology

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 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 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 provides a batch calibration method and device based on a GE function, and relates to the field of radiation detection. The method comprises the following steps: performing energy calibration on target to-be-detected equipment according to a preset acquisition mode under a standard source, and obtaining first energy spectrum data corresponding to the target to-be-detected equipment based on the energy calibration; performing dead time correction operation on the first energy spectrum data; inputting the first energy spectrum data after the dead time correction into a GE energy spectrum correction model, and outputting second energy spectrum correction data based on the GE energy spectrum correction model; integrating the second energy spectrum correction data based on a polynomial weight function to calculate a dose rate corresponding to the target to-be-detected equipment; and on the basis of the corresponding dosage rate of the to-be-detected equipment, carrying out batch calibration on the plurality of to-be-detected equipment. The problem that the whole calibration process consumes a large amount of time due to the fact that data collection, analysis and calculation of GE function parameters are needed for multiple times in the calibration process of a traditional radiation calibration method is solved.

A Flash beam dose control method and a related device. The Flash beam dose control method comprises: obtaining a Flash beam output dose demand; controlling, by means of a Flash tuning mode, the number of pulse periods of output beam charges within a preset time; and / or controlling the pulse width of an ion source voltage by means of a pulse width mapping curve, so as to control a Flash beam output dose rate. By precisely controlling the number of pulse periods of output beam charges and the pulse width of the ion source voltage, the Flash beam output dose rate can be precisely controlled without requiring an additional shielding function for a proton therapy room, so that the dose of Flash can also be tuned in a conventional proton therapy room, thereby facilitating implementation of particle Flash radiotherapy.

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

The invention discloses 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 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 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.

The invention relates to the field of semiconductor device and integrated circuit research, in particular to a semiconductor device dose rate effect laser simulation system. Multiple wavelengths and a wide energy range are achieved through the optical fiber laser pulse seed source assembly and the solid laser amplifier assembly, the pulse width can range from 1 ns to 100 microseconds, variable complex waveforms such as square waves, rectangular waves, sine waves and pulse strings are achieved, and pulse laser with the energy range from the nanojoule level to the joule level and adjustable wavelengths and waveforms can be output according to requirements. The high-low energy laser adopts a common-path design, so that the system integration degree is improved; light spots are adjustable from centimeter level to micron level, and global irradiation and micro-area positioning and scanning of an irradiation sample can be realized. According to the invention, dose rate effects under different conditions can be accurately and flexibly simulated, the blank of a high-energy, variable-waveform and multi-wavelength dose rate effect laser simulation system is filled up, and an efficient solution is provided for the reliability research of devices under a complex irradiation environment.

The invention relates to the technical field of in-vivo radiation dose determination, in particular to an in-vivo radiation dose determination method and system for nuclide therapy and a storage medium, and the method comprises the steps: measuring the energy spectrum of # imgabs0 # rays emitted in vivo for nuclide therapy within a preset duration; environment temperature and humidity at all moments within the preset duration are collected; analyzing the condition that the environment temperature at all moments deviates from a preset standard temperature range and the condition that the environment humidity at all moments deviates from a preset standard humidity range, and correcting the data of the # imgabs1 # ray energy spectrum; the characteristic complexity of the corrected # imgabs2 ray energy spectrum is determined; the optimized channel width of the # imgabs3 ray energy spectrum is obtained; and an optimized # imgabs4 ray energy spectrum is obtained by using the optimized channel width, and the in-vivo radiation dose rate of nuclide treatment is obtained. Therefore, the accuracy of determining the in-vivo radiation dose rate of nuclide therapy is improved.

The invention discloses a radiation monitoring method and gate-type radiation monitoring equipment, and relates to the technical field of radiation monitoring. The method comprises the following steps: performing pulse analysis processing on a real-time gamma ray pulse signal to obtain a real-time net counting rate and a pulse PSD distribution histogram; determining a compensation coefficient according to the environmental data, and performing real-time compensation on the real-time net counting rate to obtain a compensated real-time net counting rate; performing compensation counting rate calculation according to the reference parameter, the compensated real-time net counting rate and the pulse PSD distribution histogram to obtain a compensation counting rate; and determining a target alarm type according to the compensation counting rate, the real-time net counting rate and a preset alarm condition corresponding to each alarm type, and performing alarm control according to an alarm mode corresponding to the target alarm type. Compared with the prior art, the method does not depend on single dose rate measurement or total count rate analysis, at the moment, it can be guaranteed that detection is more accurate, the method is not affected by environmental fluctuation any more, and then the problems of frequent false alarms and the high false alarm rate can be solved.

The utility model particularly relates to an SIPM dose rate detector based on an amplifying circuit. The SIPM dose rate detector comprises a scintillator and SIPM coupling module, a pulse shaping circuit and a data receiving and displaying module. A signal amplification circuit and a voltage comparison circuit are arranged between the pulse shaping circuit and the data receiving and displaying module; the scintillator and SIPM coupling module is used for receiving input radiation energy; the pulse shaping circuit is in signal transmission connection with the output end of the scintillator and SIPM coupling module and is used for receiving signals output by the scintillator and SIPM coupling module; the signal amplification circuit is in signal transmission connection with the output end of the pulse shaping circuit and is used for receiving a signal output by the pulse shaping circuit; the voltage comparison circuit is in signal transmission connection with the output end of the signal amplification circuit and is used for receiving a signal output by the signal amplification circuit; the output end of the voltage comparison circuit is in signal transmission connection with the data receiving and displaying module. The structural design of the SIPM dose rate detector is helpful for improving the sensitivity of the SIPM dose rate detector.

The invention relates to a method for radiation detection chip angle response compensation. The method comprises the following steps: step 1, testing the counting rate of deposition of each channel of array SiPM when gamma rays have different incident angles; 2, according to a standard dose rate value and the counting rate of each channel of the array type SiPM at different incident angles obtained in the step 1, constructing a linear equation set; 3, solving the system of linear equations in the step 2 to obtain an angle response correction matrix; and 4, correcting the angle response of the chip according to the angle response correction matrix in the step 3. According to the invention, the angle response compensation of the thin-layer scintillator radiation detection chip on the directional dose rate of different incident angles is realized, and the problem of measurement deviation of the radiation detection chip caused by the change of the incident angle of the radiation source is solved.

The present application discloses a radiation dose rate assessment method, device, storage medium and equipment in three-dimensional space, which belongs to the field of radiation detection technology. The concentration data and physical parameter data of the radioactive nuclide at least one first position point in the three-dimensional space are obtained; the three-dimensional convolution of the photon flux rate of the second position point is determined, and its final kernel function is the kernel function composed of the interpolation basis functions of the first position point and the second position point obtained by approximating the original kernel function according to the FMM; the concentration data and the physical parameter data are convoluted using the three-dimensional convolution to obtain the target photon flux rate; the radiation dose rate in the three-dimensional space is assessed based on the physical parameter data and the target photon flux rate. The present application can quickly calculate the radiation dose rate of continuous and arbitrary discrete positions, reducing the computational complexity and computational cost; it can assess the radiation dose rate of complex building scenes based on the shielding matrix, and accelerate the dose calculation and improve the calculation accuracy through the nested grid FMM.

The invention discloses a calorimeter and method for FLASH radiotherapy rays. The calorimeter comprises a calorimetric core, a jacket layer and a shielding layer. The calorimetric core is an absorber of FLASH radiotherapy rays, and the calorimetric core is nested in a first space in the jacket layer in a manner that a first interval exists between the calorimetric core and the jacket layer and the calorimetric core and the jacket layer are not in contact with each other; the jacket layer is nested in a second space in the shielding layer in a manner that the jacket layer and the shielding layer have a second interval and are not in contact with each other; no non-gas filler exists in the first interval and the second interval. Through the arrangement, the calorimeter aims to meet the strict requirements of ultrahigh dose rate and millisecond irradiation of FLASH radiotherapy rays, the defects that solid filler hinders heat transfer and increases heat capacity in the prior art are overcome, through the design that three layers do not make contact with each other and are free of solid filling, heat loss and heat conduction lag are reduced, heat is concentrated on the calorimetric core, and the heat loss is reduced. Meanwhile, the overall heat capacity is reduced, the millisecond-level thermal response speed is guaranteed, and high accuracy and traceability of dose measurement are guaranteed.

The application provides a method and device for monitoring the dose of an X-ray machine, the method comprising: obtaining a functional relationship between the dose rate of the X-ray machine at a preset detection position and the exposure parameter of the X-ray machine when the X-ray machine operates at a preset frame rate; calculating the dose rate at a target detection position when the X-ray machine operates at a target frame rate and a target exposure parameter according to the functional relationship, the distance between the preset detection position and the target detection position relative to the focal point of the X-ray machine tube; calculating the cumulative dose of the X-ray machine at the target detection position according to the dose rate and the exposure time of the X-ray machine; and calculating the cumulative dose-area product of the X-ray machine according to the cumulative dose and the field area of the X-ray machine at the target detection position. The method and device for monitoring the dose of the X-ray machine can realize accurate measurement of the dose rate, cumulative dose and cumulative dose-area product of the X-ray machine through software, can balance low cost and high accuracy dose monitoring, and has a wide range of applications.

The invention discloses a radiation dose measuring device and method, the device comprises a foil, an ultrasonic pulse receiver and a signal collector, and a liquid transmission medium is filled between the foil and the ultrasonic pulse receiver; the foil is used for receiving radiation and generating ultrasonic waves, and the ultrasonic waves are transmitted to the ultrasonic pulse receiver through the liquid transmission medium; the ultrasonic pulse receiver is used for detecting ultrasonic waves and transmitting detected waveforms to the signal collector, and the signal collector is used for reading the amplitude of the ultrasonic waves and converting the amplitude into the radiation dose according to the relation between the amplitude and the radiation dose. The device and the method disclosed by the invention can realize real-time measurement of radiation dose, especially high dose rate.

This invention enables highly accurate sample analysis by analyzing energy spectra obtained using a radiation detector, even under a high dose-rate environment. In a radiation analysis method disclosed here, first, a spectrum of a sample (measured spectrum) is measured by a radiation detector (sample measurement step: S1). The measured spectrum is obtained for each of different setting conditions, where a plurality of scintillators having different sizes and a plurality of shields having different thicknesses are used, respectively. Next, similar measurement is performed on a reference source (reference source measurement step: S2). Next, from reference spectra thus obtained in S2, a background nuclide-originating component, which is a component originating from a background nuclide (137Cs) included in the measured spectra, is estimated (background nuclide-originating component estimation step: S3). Next, a corrected spectrum is calculated as the difference between the measured spectrum and the background nuclide-originating component (corrected spectrum calculation step: S4).

The invention relates to the technical field of malignant tumor treatment equipment, and discloses a scintillator excitation sensitizer system applied to malignant tumor 125 iodine particle treatment. Comprising a three-dimensional modeling module used for obtaining imaging data of tumor tissues and constructing a three-dimensional model; the radiation prediction module is used for calculating radiation dose rate space-time distribution around each radiator based on the 125 iodine particle cylinder radiator model, and forming an overall radiation dose rate space-time distribution prediction model through superposition; the positioning calculation module is used for determining the optimal placement position of the scintillator in the tumor tissue in combination with the three-dimensional model and the radiation dose rate space-time distribution prediction model; and the guiding module is used for generating a scintillator implantation path and guiding the puncture device to accurately implant the scintillator into the optimal implantation position. The optimal positioning of the scintillator in the tumor is realized, and the key problems of low-energy gamma ray energy conversion efficiency and safety are solved.

The invention relates to the technical field of radiation identification, and provides a personal dosimeter abnormal radiation identification method and system based on a time sequence LSTM, and the method comprises the steps: carrying out the abnormal value filtering, denoising and feature transformation processing of original dose rate data and environment parameter data collected by a personal dosimeter, and obtaining multi-dimensional time sequence feature data; inputting the multi-dimensional time sequence characteristic data into a long short-term memory neural network model for reasoning processing to obtain abnormal probability data reflecting the current radiation state; based on the abnormal probability data and the current environment background parameters, obtaining abnormal probability discrimination data through adaptive threshold dynamic adjustment; and performing multi-stage judgment processing on the abnormal probability judgment data to obtain an abnormal radiation identification result. According to the method, the false alarm rate caused by environment background fluctuation and the omission ratio of weak abnormal signals are reduced, and the progressive abnormity and the sudden abnormity are accurately recognized.

The application discloses a kind of point kernel integration calculation model efficient modeling method based on scene three-dimensional model, comprising: the three-dimensional modeling program is imported to nuclear facility scene three-dimensional model and the object to be modeled is split;For shielding type object, the shielding calculation model is obtained by copying on the basis of the three-dimensional model, the shielding calculation model is named, until the processing of all shielding type objects is completed;Determine the position of radioactive source term, when there is radiation field measured data, establish the quantitative mapping of dose rate and color, convert measured data into corresponding spatial position color ball-shaped measuring point to assist positioning;Source term calculation model is established by copying at the source term position and write material, nuclide and activity information;The parameters of the shielding calculation model and the source term calculation model are extracted by secondary development script and basic body information extraction algorithm;The parameters are stored according to point kernel integration calculation program input card format, and the point kernel integration calculation model for γ radiation field calculation is obtained.

A radiotherapy planning apparatus includes processing circuitry. The processing circuitry obtains a medical image relating to a patient. The processing circuitry obtains number of beams and beam directions of a plurality of radiation beams applied substantially simultaneously to an irradiation area of the patient. The processing circuitry generates a total dose rate distribution which is a spatial distribution of total values of predicted dose rates of the radiation beams to be applied to the patient, based on the medical image and the number and the direction of the radiation beams.

The application relates to a ratio type radiation sensing device with nonlinear response to dose rate and a use method thereof, and relates to a scintillator radiation measuring device with nonlinear change of luminous intensity and use method, and aims to solve the technical problems of low measuring precision, complex structure, poor reliability, poor real-time performance and poor applicability of existing radiation sensors. The ratio type radiation sensing device with nonlinear response to dose rate comprises an X-ray excitation module, a mixed sensing probe and a light signal collection module; wherein the mixed sensing probe is a round piece pressed by uniformly mixing NaLuF4:3Pr,5Er nanocrystals and NaLuF4:3Ce nanocrystals. The use method of the device is a standard curve method. The device can realize accurate detection in a wide range of 1.86-14.95 mGy / s, and can be used in the fields of environmental monitoring, biomedical imaging and public security inspection.

An embodiment of the invention relates to a method for estimating a dose rate based on measurements performed by a gamma camera (2), the gamma camera defining an observation field (Ω), the estimated dose rate originating from a radiation source (10 a , 10 b ), these radiation sources emit ionizing electromagnetic radiation; the observation field is discretized into a grid; the gamma camera (2) includes pixels (2 j ), each pixel being configured to detect ionizing electromagnetic radiation during an acquisition time and thereby forming an energy spectrum, each pixel being associated with at least one point of a grid, said pixels together allowing to obtain the position of a radiation source in an energy band or in a plurality of energy bands in the observation field; the method comprising estimating a dose rate produced on a gamma camera by a point of the grid.

This invention belongs to the field of radiation mutagenesis technology, and relates to a method for mutagenesis of lavender seeds, employing... 60 Lavender seeds are treated with Co-γ rays; the radiation dose is 50-500 Gy, and the dose rate is 1-3 Gy / min. This invention employs... 60 Radiation with Co-γ rays can efficiently induce mutations in the genetic material of lavender seeds, effectively breaking gene linkage and significantly increasing the mutation frequency. This provides a rich material basis for screening lavender mutants, allowing for the selection of seed half-lethal doses, and obtaining plants with variations in leaf color, leaf shape, plant height, and other traits. This provides technical support for lavender breeding using radiation mutagenesis technology.