281results about "Dosimeters" patented technology

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

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

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

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

The invention discloses a crystal compound, a preparation method thereof and application of the crystal compound in X-ray detection, imaging and anti-counterfeiting encryption, and belongs to the technical field of crystals. The molecular formula of the crystal compound is [Cu (totp) (CH3CN) 3] [Cu2I3 (totp) (PN)]. (CH3CN), wherein totp is tris (o-tolyl) phosphine; and PN is diphenyl-2-pyridine phosphine. The crystal compound disclosed by the invention is simple in preparation method, and has the characteristics of large mass attenuation coefficient of X-ray energy, high light yield and low detection limit when being used as a material of an X-ray detector. The compound also has the characteristic of structural transformation in solvents such as methanol, ethanol, acetone, dichloromethane, tetrahydrofuran and the like, and meanwhile, the conversion of luminescence color under the excitation of 365nm ultraviolet light and X rays is accompanied. The material can be applied to the aspects of scintillator materials, room-temperature X-ray radiation indirect detection materials, radiation detection dosimeters, X-ray scintillator medical imaging, anti-counterfeiting encryption and the like.

The invention provides a radiation environment online monitoring method and system based on the Internet of Things, and belongs to the technical field of Internet of Things monitoring, and the method comprises the steps: taking a space where radiation equipment is located as a first radiation environment space, and taking a neighborhood space as a second radiation environment space; double spaces are monitored online through an Internet of Things device group, and a first radiation environment monitoring set and a second radiation environment monitoring set are obtained; monitoring credibility correction is carried out on the two monitoring sets according to the Internet of Things equipment group, and a first environment monitoring sequence and a second environment monitoring sequence are constructed; predicting the corresponding space according to the first and second environment monitoring sequences to obtain first and second radiation safety accident features; radiation safety accident coupling prediction is carried out according to the two accident characteristics, and a radiation safety accident atlas is established; the technical problem of poor radiation safety management effectiveness caused by low radiation environment on-line monitoring precision in the prior art is solved, and the technical effects of improving the radiation environment on-line monitoring precision and improving the radiation safety management effectiveness and quality are achieved.

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 technical field of radiation protection and environment monitoring, and particularly discloses a radioactive waste gas emission radiation dose real-time monitoring system which comprises a fixed monitoring base station network, an autonomous mobile monitoring cluster, a data fusion and cooperative control center and a radiation dose field three-dimensional reconstruction and evaluation terminal. Through air-ground cooperative monitoring, plume prediction and intelligent path planning based on an atmospheric diffusion model, and a physically constrained spatial interpolation algorithm, efficient tracking of a radioactive plume three-dimensional dynamic diffusion process and accurate reconstruction and visual evaluation of a three-dimensional dose field are realized. According to the system, an air-ground cooperative monitoring system composed of a fixed base station network and an autonomous mobile cluster is constructed, so that a passive and static monitoring normal form is fundamentally changed.

The invention belongs to the technical field of radioactive metal isotope ion chromatographic separation, and discloses a medical radioactive isotope purification multichannel ion liquid chromatography system. The system comprises an automatic sample injection system, a parallel sampling and leaching channel, a parallel multi-column chromatographic structure, an online radiation dose monitoring module, a multi-channel tail end detection system, a recycling structure and a central control system. By adopting a full-automatic sample injection and multi-channel parallel chromatography structure, parallel separation, real-time radiation monitoring, multi-mode online detection and closed-loop recovery are realized, and the problems of insufficient nuclear purity, low separation efficiency, low target recovery rate and high radiation exposure of a traditional method are solved.

The invention provides a radioactive internal pollution detection method and system based on a dynamic efficiency scale, and the method comprises the steps: carrying out the detection of the radioactive internal pollution based on a pre-obtained change table of the total detection efficiency of a detector for the radionuclide in a human body along with the time; determining the total detection efficiency of the radiation detector on the radionuclides in the human body according to the interval time and the types of the radionuclides; and obtaining the activity of the internal pollution radionuclides based on the characteristic gamma ray full-energy peak counting and the total detection efficiency of the radiation detector on the radionuclides in the human body. In-vivo metabolism behaviors of nuclides are considered, so that the internal pollution detection accuracy is greatly improved. The problems that in the prior art, equipment is large in size, high in manufacturing cost, long in measurement time consumption, complex in operation and the like are solved. The method is suitable for rapid detection and classification of mass personnel in nuclear and radiation accident emergency sites.

The invention discloses a method, a circuit, a system and a medium for testing a total ionizing radiation dose and an electromagnetic pulse coordination effect, and relates to the technical field of anti-nuclear and radiation hardening, and the method comprises the steps: obtaining an electrical characteristic curve of a to-be-tested transistor before irradiation and a response waveform under the action of a single electromagnetic pulse; performing at least one preset dose of irradiation on the to-be-tested transistor until the accumulated irradiation dose of the to-be-tested transistor reaches the preset total dose, and obtaining an electrical characteristic curve of the to-be-tested transistor and a response waveform of the to-be-tested transistor under the action of a single electromagnetic pulse after each irradiation, obtaining an electrical characteristic curve and a response waveform of the transistor to be detected under each accumulated irradiation dose; and based on the obtained electrical characteristic curve and the response waveform, analyzing the total ionizing radiation dose of the transistor to be detected and the electromagnetic pulse coordination effect.

An online detection method, detector, and detection system for accelerator X-ray energy are disclosed. The online detection method includes irradiating a test field with multiple X-rays of known energies by the accelerator; acquiring first measurement values ​​of the first X-rays after passing through absorbers of different thicknesses using a detector module; obtaining a first absorbed dose value from the first measurement value; establishing a first relationship curve based on the first absorbed dose value and forming a set of standard curves; irradiating the test field with second X-rays by the accelerator; establishing a second relationship curve corresponding to the energy of the second X-rays; including the second relationship curve in the set of standard curves; and determining the energy of the second X-ray based on the energy interval between the two adjacent first relationship curves. By analyzing the relationship between the measured values ​​received by the detector module and the thickness of the absorber at the incident end of the detector module with the X-ray energy, online detection of the X-ray energy irradiated by the accelerator can be achieved.

A radiation dose quantification method and system, the method comprising: detecting, with one or more detectors with respective sensitive volumes, gamma-rays emitted as a result of capture of neutrons by a composition in a subject subjected to an irradiation program, the composition comprising one or more thermal neutron capture agents, the neutrons having been generated by non-elastic collisions between a primary beam of particles and nuclei in the subject, wherein the particles consist of any one or more of protons, deuterons, tritons and heavy ions, the irradiation program comprises at least one period of irradiation with a beam duration that includes beam-on periods and beam-off periods; applying at least one predefined energy window or filter configured to accept only detection events in the one or more detectors resulting from gamma-rays with an energy indicative of selected gamma-rays arising from the capture of thermal neutrons by the one or more thermal neutron capture agents, wherein the thermal neutrons are neutrons with energies below approximately 0.4 eV; applying a timing window configured to reject or ignore detection events in the one or more detectors resulting from at least prompt gamma-rays produced in non-neutron capture events; and determining the radiation dose of neutron radiation received by the subject during the irradiation program from at least the accepted detection events or determining a dose map of the radiation received by the subject from at least the accepted detection events.

The invention relates to a computer-implemented method for determining spatially resolved radiation load information of a patient when conducting an examination with an imaging X-ray apparatus having an X-ray radiator for outputting an X-ray field for conducting the examination, wherein patient input dose information is determined for determining the radiation load information, wherein the pre-dose information is determined in the case of use of a matching filter arranged between the patient and the X-ray radiator, which causes a non-uniform dose distribution in a plane perpendicular to a central ray of the X-ray field, the pre-dose information describing a uniform distribution of the X-ray dose acting on the patient without the matching filter; dose distribution information is calculated using the pre-dose information by means of a filter model, which describes at least the dose distribution of the X-ray dose acting on the patient in the part of the X-ray field covered by the matching filter; and the patient input dose information is determined using the dose distribution information.

The utility model discloses a radioactive ray isolation device in the technical field of isolation devices, which comprises a placing frame, a plurality of lead plates are welded on the surface of the placing frame, and a through groove is arranged on the surface of the placing frame; the device comprises a through groove, two lead curtains are arranged on the inner wall of the through groove, the device further comprises an installation unit and a detection unit, the installation unit is used for installing the two lead curtains on the inner wall of the through groove, and the detection unit is used for monitoring the radiation amount of radioactive substances in the through groove. According to the lifting device, the lifting frame is arranged above the two main frame bodies, and when the lifting device is used, a user can control the two electric push rods to stretch out and draw back through the controller, so that the lifting frame fixedly installed at one ends of the two electric push rods is driven to ascend and descend, and the distance between the inner wall of the lifting frame and a conveying belt below the lifting frame is controlled; and therefore, belt conveyors with different heights can be adapted.

The application discloses a kind of nuclear power plant power operation mode pipeline deposition source item background evaluation system and method, this method includes: S1.the activity ratio ε of activated corrosion product nuclide i is measured i , pipe surface dose rate D and the activity concentration C of nuclide i in primary coolant i ;S2.modeling and calculating the effective dose rate D of pipe surface by activated corrosion product in deposition contribution d ;S3.modeling and calculating the surface activity of activated corrosion product nuclide i in deposition source item;S4.modeling and calculating the total count rate CPS or total absorbed dose rate Gy / h of pipeline deposition source item to detector.The nuclear power plant power operation mode pipeline deposition source item background evaluation system and method of the application, the activity ratio of activated corrosion product nuclide i, pipe surface dose rate, the activity concentration of nuclide i in primary coolant are measured, modeling and calculating the total count rate CPS or total absorbed dose rate Gy / h of pipeline deposition source item to detector, realize the evaluation of deposition source item background under the power operation mode of unit.

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 invention discloses a full-automatic gas-state and aerosol-state iodine combined measurement device and a measurement method. A sampling measurement module, a storage module, a recovery module and a three-axis movement mechanism are integrated in a case; the horizontally arranged sampling and measuring module comprises an aerosol-state iodine sampling and measuring cavity and a gaseous iodine sampling and measuring cavity which are arranged side by side, and the aerosol-state iodine sampling and measuring cavity is used for accommodating and sealing a filter paper sheet and is provided with an aerosol-state iodine monitoring unit gas inlet and an aerosol-state iodine monitoring unit gas outlet; the gaseous iodine sampling and measuring cavity is used for accommodating and sealing an iodine box and is provided with a gaseous iodine monitoring unit gas inlet and a gaseous iodine monitoring unit gas outlet. Synchronous, rapid and online combined continuous measurement of gaseous iodine and aerosol-state iodine at the same sampling point is realized, the accuracy of a measurement result can be improved, sampling and measurement can be performed synchronously, rapid measurement of an instrument is realized, and richer nuclide type information can be obtained.

The application discloses a real-time processing method for missing data of a regional radiation monitor, and relates to the technical field of data processing. The method comprises the following steps: acquiring in-door radiation sequence data and out-door radiation sequence data generated in the operation process of the regional radiation monitor in a historical time period; determining a drug injection time based on fluctuation characteristics of the in-door radiation sequence data; determining an out-door performance time based on a time correspondence relationship between the drug injection time, the in-door radiation sequence data and the out-door radiation sequence data; comparing a plurality of suspected out-door performance times before a current time with the out-door performance time in the historical time period to obtain a real probability of the suspected out-door performance time; judging a radiation fluctuation completeness degree of the in-door radiation sequence data processed by a linear interpolation method based on the real probability; and generating a required data compensation measure based on the radiation fluctuation completeness degree. The application achieves the technical effect of improving the judgment accuracy of abnormal radiation events.

The invention relates to a circuit and a method for measuring the threshold voltage of a PMOS (P-channel Metal Oxide Semiconductor) transistor in a radiation environment, in particular to an on-chip measuring circuit and a method for the threshold voltage of the PMOS transistor and a total radiation dose monitoring circuit, and solves the problem that the existing device for measuring the threshold voltage of the PMOS transistor cannot monitor the change of the threshold voltage on line. Or the size is large and the precision is low. According to the on-chip measuring circuit for the threshold voltage of the PMOS transistor, a differential mode is adopted, the subtracter circuit is used for sampling the voltage at the source end and the drain end of the PMOS transistor, common-mode noise generated by the outside to a measured signal can be effectively eliminated, the on-chip measuring circuit can be realized, the size and the weight of the measuring circuit are effectively reduced, and the cost is reduced. And real-time monitoring of the threshold voltage of the PMOS transistor is realized. Meanwhile, the invention further provides a total radiation dose monitoring circuit, signals are processed and amplified at the near end of the PMOS transistor, the strength and the anti-interference capacity of the measured signals can be effectively improved, and the size is further reduced.

The invention discloses an X-ray detection method and device based on a perovskite material and a medium, and relates to the technical field of signal processing, and the method comprises the steps: collecting a layered structure and a fluorescence signal, obtaining a structure parameter set, carrying out black field signal collection and multi-dose flat field calibration, and obtaining an initial non-uniformity correction parameter table; collecting a disturbance response signal, calculating a trap load indicating quantity, obtaining a trap state index and a suggested bias voltage adjusting quantity, and obtaining a stable working bias voltage and a trap state flag by adopting proportional-integral adjustment; collecting a photoelectric dual-channel signal, performing offset deduction and response correction according to the correction parameter table, and adaptively adjusting a fusion weight according to a trap state to obtain a fusion dose value and a pixel dose graph; and based on the fusion result, performing small-step iteration to update the correction parameter, calculating a detection quality index in combination with a trap state flag, and outputting a final dose graph. According to the invention, the fusion weight is adjusted according to the trap state through the photoelectric dual-channel signal, and the high-precision estimation of the fusion dose is realized.

The application discloses a kind of nuclear power plant radiation environment monitoring method and system, method includes: collecting nuclear power plant radiation environment real-time monitoring data, obtains environmental monitoring real-time data set;Dynamic threshold comparison is carried out to environmental monitoring real-time data set, generates abnormal mark or normal feature vector;In the case where no abnormal mark is generated, normal feature vector is input into pre-trained environmental trend prediction model, and the radiation environment change trend curve and potential anomaly probability in future preset time period are output;Based on change trend curve and potential anomaly probability, generate early warning information of grading, finally output the monitoring early warning result containing early warning level, prediction timeliness and coping strategy.Utilize the embodiment of the application, it can realize the whole process intelligent monitoring from abnormal identification to prediction intervention to radiation environment, improve early warning accuracy, timeliness and decision support capability.

The invention discloses a radiopharmaceutical dose automatic calibration method, which comprises the following steps of: performing charge state analysis on an iodine-131 radiopharmaceutical solution to determine the polarity and the intensity of an electrostatic charge required to be applied by a needle; before injection, static charges are applied to the needle head through the micro-current generating device, so that medicine can be effectively separated from the needle head after injection is completed, and residues are reduced; a high-precision micro-injection pump is combined with a pressure sensor to control the injection speed and dose output, and the fluid flowing state is monitored in real time to avoid abnormal conditions; after injection, a laser scattering detection module and an image recognition algorithm are used for capturing and evaluating the volume of residual liquid drops at the tail end of a needle head in real time, the dose needing to be additionally supplemented is calculated according to the volume, and it is ensured that a patient receives the accurate target dose; no needle residue is confirmed again after dose supplementation, so that the accuracy of the final administration dose is ensured; the whole system is flexible and high in adaptability, and can be adjusted according to the characteristics of different types of radiopharmaceuticals.

A radiation dose quantification method and system, the method comprising: detecting, with one or more detectors with respective sensitive volumes, gamma-rays emitted as a result of capture of neutrons by a composition in a subject subjected to an irradiation program, the composition comprising one or more thermal neutron capture agents, the neutrons having been generated by non-elastic collisions between a primary beam of particles and nuclei in the subject, wherein the particles consist of any one or more of protons, deuterons, tritons and heavy ions, the irradiation program comprises at least one period of irradiation with a beam duration that includes beam-on periods and beam-off periods; applying at least one predefined energy window or filter configured to accept only detection events in the one or more detectors resulting from gamma-rays with an energy indicative of selected gamma-rays arising from the capture of thermal neutrons by the one or more thermal neutron capture agents, wherein the thermal neutrons are neutrons with energies below approximately 0.4 eV; applying a timing window configured to reject or ignore detection events in the one or more detectors resulting from at least prompt gamma-rays produced in non-neutron capture events; and determining the radiation dose of neutron radiation received by the subject during the irradiation program from at least the accepted detection events or determining a dose map of the radiation received by the subject from at least the accepted detection events.

The invention relates to a flat plate ionization chamber capable of measuring beta, X and gamma rays and a use method thereof, one side of an ionization chamber main body is provided with an incident window film, the incident window film side is provided with a balance cover, the balance cover is provided with a vent hole, and the vent hole is arranged on a circular plane of the balance cover; the spring needle is arranged in the ionization chamber main body and is in contact connection with the incident window film; the spring needle stud is located at the rear end of the spring needle, abuts against the rear wall of the ionization chamber body and is used for abutting against the spring needle to make continuous contact with the incidence window film. And the high-voltage conductive column is connected with the spring needle, is connected with an external power supply and is used for applying voltage to the incident window film through the spring needle. The balance cover is arranged in front of the ionization chamber main body, the balance cover provides a secondary electron balance condition for the ionization chamber to measure the strong penetrating radiation, the strong penetrating radiation can be measured by the ionization chamber, on the contrary, when the balance cover is removed, the weak penetrating radiation can be measured by the ionization chamber, and the strong penetrating radiation and the weak penetrating radiation can be measured by one ionization chamber. And the effect of weak through radiation can also be measured.