531 results about "Radiation dose" patented technology

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

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

The invention discloses a method and a system for determining optimal parameters of an X-ray excited extra-high voltage composite apparatus, and relates to the technical field of extra-high voltage electrical equipment detection. The method comprises the following steps: remotely operating the X-ray machine and calculating partial discharge intensity; for the current irradiation position, the tube voltage and the tube current are gradually adjusted, parameters are dynamically optimized based on the quantitative relation between the partial discharge intensity and the radiation dose rate change rate, and the optimal parameters are recorded; and changing position repetition parameter optimization, and constructing a BP neural network model after data set training optimization so as to predict an optimal irradiation position. The optimized BP neural network adopts an improved sparrow search algorithm to optimize an initial weight and a threshold value, and combines Bayesian to optimize a learning rate and a hidden node number. Accurate optimization of excitation parameters and irradiation positions is achieved, detection accuracy and safety are both considered, the optimal irradiation position positioning efficiency is improved, and the method is suitable for ultra-high voltage GIS detection of different voltage grades.

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

The invention provides a radiation dose evaluation method and system based on radiation environment monitoring data, and relates to the technical field of radiation environment monitoring. The method comprises the following steps: recording the release source intensity of each nuclide at a release point, drawing an equally-spaced concentric arc grid, calculating the release height by combining the ground and the release point air pressure, air density and gravitational acceleration, and assigning nuclide hazard factors to the outer edge of the grid; according to the distance between the release point and the outer edge of the grid, diffusion parameters are calculated by using an empirical formula, a Gaussian atmospheric diffusion model is constructed in combination with the release height and hazard factors, and nuclide air activity concentration is output; comparing the total effective dose with a preset threshold value to calibrate a diffusion range, quantifying the radiation dose per unit area, and dividing atmospheric stability coefficient grades; constructing three types of correction factors of release height, material state and weather condition, establishing a comprehensive dose evaluation formula by combining the unit area radiation dose and the correction factors, comparing a preset threshold value, judging a risk level, and performing periodic updating.

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

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

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

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

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

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

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

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

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

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

Methods and computing apparatus for implementing a radiation dosimetry process. An example process may include exposing a first radiation sensitive film to a series of known doses of radiation, measuring a first set of radiation data with a measurement device, and determining a calibration curve. The calibration curve may be determined by selecting Raman spectral ranges based on the first set of radiation data, determining a plurality of band area ratios, and generating the calibration curve based on plotting the band areas and ratios compared to known dose. The radiation dosimetry process then exposes a second radiation sensitive film to an unknown dose of radiation, measures a second set of radiation data for the second radiation sensitive film with the measurement device, and determines a dose exposure level for the second radiation sensitive film by comparing the second set of radiation data with the calibration curve.

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 discloses a radiation dose detection method and system for an irradiation cross-linked area, and belongs to the technical field of radiation dose detection.The method specifically comprises the steps that coordinates of a to-be-detected core point and coordinates of related points around the to-be-detected core point are input, and transient fluorescence spectrums, thermoluminescence signals and conductivity change data of all the points in an irradiation window are synchronously collected; constructing a physical configuration association model based on association point distribution, and forming a scattered field association data network; when the residual error between the actually measured data of the core point and the model predicted value exceeds a dynamic threshold value, activating the reverse solving process of the scattered field, reversely reconstructing a theoretical data sequence of the core point by using associated node data, and replacing interfered original data; and finally, inputting the reconstructed sequence into a dose calculation model, and outputting a corrected radiation dose value. According to the invention, measurement errors caused by local material non-uniformity and instantaneous interference can be effectively reduced, and the reliability of dose detection is improved.

The invention discloses a nuclear accident dynamic safe operation time assessment method and system based on data fusion, relates to the technical field of nuclear radiation protection, and solves the technical problems that the safe operation time is not accurate enough and dynamic dose assessment is difficult in nuclear accident emergency response. According to the technical scheme, nuclear accident prediction data and site real-time monitoring data are fused, a data assimilation fusion algorithm and an intelligent analysis model are combined, the radiation dose and environmental conditions of an accident site are comprehensively evaluated, and safety operation time and risk levels of different areas are dynamically calculated and updated; by considering the building shielding effect and supporting the federated learning framework, the cooperative evaluation of multiple monitoring points is realized, so that the operation time evaluation precision and decision-making efficiency in the nuclear accident emergency response are greatly improved. Finally, operation suggestions can be fed back and updated in real time, and the real-time performance and accuracy of emergency command decisions are ensured.

The invention relates to a respiration guiding system for image examination, which is applied to the technical field of image examination and comprises a respiration monitoring module, a patient feedback module, a control processing module and a physician interaction terminal, a plurality of different target breathing waveforms are pre-stored in the doctor interaction terminal, the control processing module generates real-time breathing waveforms based on breathing waveform signals, time synchronization is conducted on the target breathing waveforms and the real-time breathing waveforms, then the patient feedback module and the doctor interaction terminal are controlled to be displayed in a parallel comparison mode, and a patient is guided to adjust breathing. According to the invention, through ''physician-system-patient'' three-element closed-loop interaction, respiratory training and pre-judgment before scanning and continuous guidance and stable maintenance during scanning are realized, so that the success rate of first scanning is improved, the number of times of repeated scanning is reduced, and the radiation dose risk and medical cost of a patient are reduced.

The invention discloses a building group three-dimensional reconstruction and radiation dose field visualization method based on aerial images, relates to the technical field of image processing, enables the timeliness of a new visualization method to be higher, and solves the core problems of low manual modeling efficiency and poor geometric transformation universality in the prior art. Comprising the following steps: S1, collecting a multi-view image of a building group at a preset site through an unmanned aerial vehicle; s2, sparse point cloud reconstruction is carried out on the image obtained in the step S1, and a model is optimized; s3, format conversion is carried out on the sparse point cloud model and the camera pose data obtained in the step S2, dense point cloud reconstruction, grid model reconstruction and texture mapping are carried out in sequence, and a high-precision building group three-dimensional model is generated; s4, converting the three-dimensional model obtained in the step S3 into a CAD geometric model, and eliminating geometric overlapping defects in the three-dimensional model; s5, the CAD model is converted into a Monte Carlo program through a BRep-to-CSG conversion engine; and S6, configuring radiation transport parameters, executing Monte Carlo calculation, and outputting three-dimensional distribution of the radiation dose field.

The present application relates to a kind of core high probe extraction mechanism, which provides effective radiation protection during the removal of the probe by introducing a shielding cylinder, significantly reduces the radiation dose that can be received by the operator when working, improves the safety of the working environment.Secondly, the present application also configures a positioning connection device with a positioning camera, which can monitor and adjust the position of the lifting moving assembly in real time, ensure its accurate alignment with the probe to be removed, and avoid positional interference between the shielding cylinder and other structural members in the core during the gradual deepening of the shielding cylinder into the core pool, thereby solving the problem of difficult accurate docking in traditional methods, improving the probe removal efficiency and operation safety.

1. The name of the design product: radiation measuring device. 2. The use of the design product: the design product is used for monitoring the radiation dose field of the environment radiation and analyzing the radionuclide deposition characteristics. 3. The design points of the design product: in shape. 4. The picture or photo that best indicates the design points: design 1 perspective view. 5. Design 1 is designated as the basic design.

The application relates to the technical field of medical data processing, and discloses a macroscopic cross-section database construction method, a dose determination method, a device and equipment, which comprises the following steps: setting multiple boron concentration values for the tissue types corresponding to a human body model; selecting corresponding neutron source parameters for the tissue types and the multiple boron concentration values, wherein the neutron source parameters comprise energy range values; dividing the energy range values into multiple discrete neutron energy groups; performing particle transport simulation based on the selected neutron source parameters, jumping between different neutron energy groups in the simulation process, and obtaining neutron reaction rates and neutron fluxes of the tissue types under the multiple boron concentration values and the multiple neutron energy groups; and obtaining neutron macroscopic cross-section values of the tissue types under the multiple boron concentration values and the multiple neutron energy groups based on the neutron reaction rates and the neutron fluxes, and constructing a multi-group macroscopic cross-section database. The application can improve the calculation efficiency of the radiation dose and improve the adaptability to individual metabolic differences during dose calculation.

The invention relates to the technical field of cone-beam computed tomography, and discloses a scattering correction method and system for cone-beam computed tomography. The method comprises the following steps: acquiring original projection data and main scattering data acquired by a first flat panel detector; wherein the first flat panel detector is arranged in the emission direction of the radiation source; acquiring secondary scattering data acquired by a second flat panel detector; wherein the second flat panel detector is arranged in the scattering direction of the radiation source; determining target projection data based on the original projection data, the main scattering data and the auxiliary scattering data; the target projection data is used for cone beam computed tomography imaging. According to the method, scattering correction can be completed on the premise of not depending on special hardware, not additionally increasing radiation dose and not losing imaging view, and the imaging precision can be effectively improved.

The invention relates to the technical field of tumor molecular imaging, nuclear medicine diagnosis and targeted therapy, and discloses a Trop2-targeted polypeptide, a Trop2-targeted molecular probe and application of the Trop2-targeted polypeptide and the Trop2-targeted molecular probe. The polypeptide can be coupled with different imaging elements to construct molecular probes or radiopharmaceuticals for tumor targeted imaging, so that noninvasive visual detection on the Trop2 expression level in tumor tissues is realized. The probe can specifically recognize Trop2 positive solid tumors, and a new technical means is provided for noninvasive diagnosis and dynamic monitoring of various Trop2 high-expression tumors such as pancreatic cancer, lung cancer, breast cancer and thyroid cancer. The probe disclosed by the invention has the advantages of simple preparation process, low cost, high specificity and stability, short imaging period, low radiation dosage, easiness in clinical transformation and the like, and has a wide application prospect in precise diagnosis and individualized treatment of tumors.

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.