22 results about "Dose conversion" patented technology

The invention relates to the technical field of dosimetry, in particular to a rapid dose evaluation method and device for individualized targeted radionuclide treatment.The method comprises the steps that labeled nuclides, drug ligands and image data of a patient are obtained, and corresponding standard S values are selected according to the labeled nuclides and the drug ligands; the method comprises the following steps: segmenting first-time-phase CT image data to obtain a segmentation mask of a target organ, calculating an individualized S value based on the segmentation mask, generating an individualized voxel model, registering the SPECT image data and the CT image data to obtain organ-level source item parameters and voxel-level source item parameters, and calculating an individualized S value based on the individualized voxel model to obtain an organ-level source item parameter and a voxel-level source item parameter; and according to the organ-level source item parameter and the voxel-level source item parameter, respectively obtaining an organ-level dose evaluation result and a voxel-level dose evaluation result, and comprehensively evaluating source target organ dose distribution. Therefore, the problems that the dose conversion coefficient lacks calibration, the voxel model is difficult to balance the calculation speed and precision and the like are solved, errors caused by individualized differences are reduced, and the calculation accuracy and speed are guaranteed.

The invention discloses an OpenMC-based BNCT dose full-process automatic calculation output method, and particularly relates to the technical field of boron neutron capture therapy dose calculation, and the method comprises the steps: reading a DICOM-CT image, automatically completing HU value segmentation, material assignment and voxel grid modeling, and generating an OpenMC geometry and material input card; setting a neutron / photon source, an operation mode and a counting grid, and executing Monte Carlo transport calculation; an ICRP flux-dose conversion coefficient library is built in, and dose calculation is automatically completed; the dose field is written into an Rt dose file, and the Rt dose file can be directly imported into mature medical image processing software for visual evaluation and plan optimization. According to the method, end-to-end automation from the CT image to the clinical available dose file is achieved, manual intervention is not needed, the BNCT dose calculation efficiency, precision and standardization level are remarkably improved, and a reliable tool is provided for BNCT dose simulation research.

This invention discloses a method for detecting the toxicity threshold of a substance based on a rat drinking experiment. The method of this invention includes the following steps: First, a drinking preference experiment is conducted, and then the toxicity threshold is determined: the amount of substance water and pure water consumed in the drinking preference is compared to determine the time when the rat begins to significantly avoid substance water, the mass of the toxic substance in the rat's body at that time is calculated, and the toxicity threshold of the rat is calculated; (3) dose conversion from rat to human: based on the interspecies dose conversion of body surface area, the toxicity threshold of the rat is first converted into the equivalent dose for humans to obtain the acute exposure dose, and then the acute exposure dose is converted into the chronic exposure dose for humans to obtain the substance toxicity threshold. This invention can accurately determine the toxicity threshold: it achieves toxicity assessment of low-dose exposure through spontaneous recognition behavior; it is easy to operate; and it is applicable to the toxicity assessment and non-destructive threshold determination of various substances such as environmental pollutants, chemical substances, and drugs.

The application provides a parameterized real-time measurement method for field neutron energy spectrum and dose, which comprises the following steps: using a three-section function model to represent the field neutron energy spectrum; constructing simulated field neutron energy spectrums of multiple moderation levels, and using a detector to measure and calculate a thermal-fast ratio; simulating and calculating the simulated field neutron energy spectrum of a test point by using a Monte Carlo model to obtain model parameters; establishing a corresponding relationship between the model parameters and the thermal-fast ratio; measuring the fast neutron pulse count rate and the thermal neutron pulse count rate by using the detector in the field, determining the value of the model parameters by looking up a table or interpolation, and the like according to the corresponding relationship between the model parameters and the thermal-fast ratio; calculating the field neutron energy spectrum according to the model parameters, and calculating the field neutron dose by using the field neutron energy spectrum and a neutron fluence-dose conversion coefficient.

This invention provides an intravenous drug infusion dosage conversion display panel, including a support, a rotating shaft, a dosage disc, and a shielding cover. A suction cup is provided on the rear side of the support. The rotating shaft is horizontally positioned at the center of the support. The dosage disc has multiple evenly distributed dosage zones, each with a table, and each table has a first dividing strip at the line position. The dosage disc is rotatably mounted on the rotating shaft. Multiple handheld posts are provided at the edge of the dosage disc, each handheld post located at the junction of two dosage zones. The shielding cover is fixedly mounted on the front end of the rotating shaft, and the front end of each handheld post is rotatably mounted inside the shielding cover. The lower half of the shielding cover has a viewing window corresponding to one dosage zone. The viewing window of the shielding cover is located at the bottom, facilitating viewing by medical personnel. Only one dosage zone is visible, preventing medical personnel from misreading the dosage when comparing a single intravenous drug, thereby reducing the possibility of medical accidents.

The application provides a dose distribution generation method and device and electronic equipment, which can be applied to the technical field of medical image processing. The method comprises the following steps: determining an initial intensity distribution map according to a predicted dose distribution matched with target tissue contour data of a target object; optimizing the initial intensity distribution map by using a target optimization function and a target constraint condition to obtain a target intensity distribution map, the target optimization function is used to optimize the boundary beam intensity of the initial intensity distribution map in a boundary region, the target constraint condition is used to constrain the proportion of target voxels in the boundary region, which exceeds a preset boundary dose threshold, to be less than a preset proportion threshold, the boundary region represents the region of the boundary between the organ tissue region and the tumor tissue region, and the boundary conversion dose is obtained by converting the boundary beam intensity based on an intensity dose conversion factor; and determining a target dose distribution representing the deposition of simulated radiation irradiating the tumor tissue region and the organ tissue region according to the target intensity distribution map.

An apparatus, computer program, computer-readable medium, and method for setting corresponding relative laser intensities for a plurality of pixels representing a lithographic exposure. The plurality of pixels includes: at least one edge pixel located at an edge of a pixel region to be exposed; and at least one adjacent pixel arranged to be spaced apart from the at least one edge pixel by one pixel in a direction perpendicular to the edge towards the pixel region to be exposed. The method includes proportionally reducing the relative laser intensity of each pixel of the plurality of pixels from a previously set corresponding first relative laser intensity to a corresponding second relative laser intensity. The laser dose conversion of the relative laser intensity of the pixel is proportionally adjusted from a previously set first laser dose conversion to a second laser dose conversion such that the corresponding effective exposure laser dose of each pixel is achieved by the second laser dose conversion of the corresponding second relative laser intensity, and the corresponding effective exposure laser dose of each pixel is equal to the corresponding effective exposure laser dose of each pixel generated by the first laser dose conversion of the corresponding first relative laser intensity. The corresponding relative laser intensity of the edge pixel of the at least one edge pixel or the adjacent pixel of the at least one adjacent pixel is increased from the corresponding second relative laser intensity to a corresponding third relative laser intensity.

The invention relates to a pulse charged particle beam dose monitoring system and a monitoring method thereof.The pulse charged particle beam dose monitoring system comprises an ACCT sensor, a signal conditioning module, a high-speed data acquisition module and a data processing and interaction module, the ACCT sensor is installed on a beam vacuum pipeline, and the output end of the ACCT sensor is connected to the signal conditioning module; the output end of the signal conditioning module is connected to the high-speed data acquisition module, and the output end of the high-speed data acquisition module is connected with the data processing and interaction module; the method comprises the following steps: carrying out system calibration to obtain a conversion coefficient k in a preset signal-dose conversion relation; performing dose-time spectrum real-time monitoring and analysis by adopting a system; and obtaining a dose-time spectrum of the charged particle beam. By adopting the system and the method disclosed by the embodiment of the invention, real-time and non-destructive monitoring on the beam pulse time structure and the corresponding dose-time distribution can be realized, so that support and guarantee are provided for accurate dose control and safe treatment.

The invention provides a dose distribution generation method and device and electronic equipment, which can be applied to the technical field of medical image processing. The method comprises the following steps: determining an initial intensity distribution diagram according to estimated dose distribution matched with target tissue contour data of a target object; and optimizing the initial intensity distribution diagram by using a target optimization function and a target constraint condition to obtain a target intensity distribution diagram, the target optimization function being used for optimizing the boundary beam intensity of the initial intensity distribution diagram in the boundary region, the target constraint condition is used for constraining that a target voxel ratio of a boundary transformation dose exceeding a preset boundary dose threshold value in the boundary region is smaller than a preset ratio threshold value, and the boundary region represents a boundary region between the organ tissue region and the tumor tissue region; the boundary conversion dose is obtained by converting the boundary beam intensity based on an intensity dose conversion factor; and according to the target intensity distribution diagram, determining target dose distribution representing deposition of the tumor tissue area and the organ tissue area irradiated by the simulated rays.

The invention discloses an X-ray total dose determination method for an integrated circuit chip radiation effect evaluation test, and the method comprises the steps: carrying out the simulation modeling of each plate layer structure related to a radiation sensitive region in a to-be-tested integrated circuit chip, and obtaining a real structure model, simulating an X-ray irradiation environment and counting the absorbed dose of a sensitive area in the real structure model of the integrated circuit chip; performing simulation by adopting a balance model body, and layering the balance model body according to each plate layer structure of the real structure model to obtain a simulation structure model; simulating an X-ray irradiation environment and counting the absorbed dose of a sensitive area in the simulation structure model; and calculating a dose conversion factor according to the real structure model and the absorbed dose of the sensitive area of the balance die body, and correcting according to the dose conversion factor to obtain the X-ray total dose of the radiation effect evaluation test. According to the invention, the total X-ray dose is corrected through simulation calculation before the test, so that the dose accuracy in the irradiation test process can be ensured.

The application discloses a BNCT gamma dose measurement system based on sCVD diamond, wherein a sCVD diamond detector signal is transmitted to a radio frequency amplifier for conditioning and amplification, the amplified analog signal is converted into a digital signal by a high-speed ADC and is transmitted to an FPGA for processing, a trigger threshold is set to obtain effective radiation signals, and each radiation signal data point is collected; waveform data collected by the ADC is transmitted to an upper computer, discrimination of gamma signals and acquisition of air absorption dose data are completed in the upper computer, firstly, the radiation signals are subjected to filtering and normalization processing; secondly, the processed radiation signals are input into a neutron-gamma discrimination program for processing, and the radiation signals in the discrimination results are input into an air absorption dose conversion program to obtain final gamma dose information. The application integrates the functions of a diamond detector, an ADC and an FPGA, cooperates with modularized design of each part, so that the detection method can realize real-time collection in a high-dose-rate neutron gamma mixed field, can effectively discriminate gamma signals and can obtain a gamma dose rate, and has high practicability.

The invention provides a biomarker for an intrathecal analgesic administration dosage conversion ratio and a determination method and system.The biomarker is selected from a # 9 region and a # 16 region of promoter regions of an ABCB1 gene and comprises a primer sequence at the 5'end of the # 9 region; a 3'end primer sequence of the # 9 region; a 5'end primer sequence of a # 16 region; and a 3'end primer sequence of the # 16 region. According to the invention, the methylation degree of two promoter regions of the ABCB1 gene is detected, and a proper dosage conversion ratio is judged when oral administration is converted into intrathecal administration, so that a rapid, effective and safe dosage scheme is provided for intrathecal analgesia patients; the individualized conversion proportion is selected according to the methylation degree, and the intrathecal dose titration speed is increased; the intrathecal analgesia patients are classified according to the methylation degree, and the corresponding dosage conversion proportion is selected; according to a methylation degree detection result, an oral administration dosage conversion ratio and an intrathecal administration dosage conversion ratio are classified, the intrathecal analgesic dosage is accurately guided, and the dosage titration efficiency is improved.

The invention discloses an experimental animal organ dose evaluation method based on digital twinning, and relates to the technical field of radiation dose evaluation, and the method comprises the steps: constructing an experimental animal digital phantom; the digital phantom comprises main organs and tissues of an experimental animal; a digital simulation platform of a microscopic CT system is constructed based on Monte Carlo particle transport simulation, and a radiation transfer process in CT scanning is simulated; constructing a micro-CT dose index phantom, simulating dose detection of the metal oxide semiconductor field effect transistor, and recording an average dose value under a simulation condition; calculating a dose conversion coefficient of the digital simulation platform by comparing a micro-CT dose index result calculated in the digital simulation platform with an actually measured micro-CT dose index result; establishing an organ dose conversion coefficient table; the actual absorbed dose of each organ is calculated; and storing the organ dose data and dose conversion coefficients of different types of experimental animals under different scanning parameters into a database.

The invention discloses a drug administration dosage measuring method and system based on laser ranging, and relates to the technical field of medical instrument metering control, and the method comprises the steps: collecting the moving distance of a push rod, the volume of an injector and the length specification parameter of a needle cylinder, inputting the collected volume of the injector and the length specification parameter of the needle cylinder into an interactive interface, and building a geometric conversion basis; constructing a dynamic metering conversion function, calculating a conversion scale factor, and inputting the conversion scale factor, the movement distance of the push rod and the specification parameters of the injector into the dynamic dose conversion function to obtain an injection dose value; and organizing the injection dosage value, the initial displacement and the injector model data in a structured form, and storing and outputting the organized injection dosage value, the initial displacement and the injector model data. According to the method, a dynamic metering conversion function is constructed, and a conversion scale factor is dynamically adjusted by adopting a relative displacement proportion driving period adjustment function.

The application discloses a data conversion and output method and system for CANDU reactor radiation dose simulation, relates to the technical field of nuclear engineering safety analysis and computer simulation, and comprises the following steps: obtaining original dose data in the unit of (Sv / s) / (Bq / m3) in a nuclear safety analysis report, automatically converting the original dose data into dose conversion factors in the unit of (Sv / s) / (individual / m3) based on a decay constant, and performing working condition adaptability correction on the dose conversion factors in combination with at least one of heavy water moderation characteristics, horizontal pressure tube geometric effects and double-loop asymmetric source term distribution characteristics to obtain corrected dose conversion factors; simulating the total number of captured radionuclide atoms, multiplying the total number of captured radionuclide atoms by the corrected dose conversion factors after volume standardization to obtain an instantaneous dose rate, and then performing time integration on the instantaneous dose rate to obtain a cumulative dose, and automatically converting the cumulative dose into an mSv order output, so that the calculation efficiency, simulation accuracy and engineering usability are significantly improved.

The invention discloses a medicine precise conversion system, electronic equipment and a storage medium, and relates to the technical field of medical data processing, the system comprises a multi-source data acquisition module used for interacting an HIS system and an EMR system to obtain basic information and personalized information of a target user; the medicine dosage conversion prototype matching module is used for matching in a medicine dosage conversion prototype library based on the basic information and the personalized information to obtain a target medicine dosage conversion prototype and outputting a target medicine dosage conversion scheme; and the user interaction module is used for screening verification information from the dynamic verification library and sending the verification information to a target user, and the target user obtains a target drug dose conversion scheme. The technical problems that in the prior art, medicine dose conversion is not accurate enough, system interactivity is poor and data management safety is insufficient are solved, and the technical effects that medicine dose conversion is accurate, and system interactivity and data management safety are improved are achieved.

The present invention relates to the field of CT image modeling technology, and in particular to a method for converting CT images into a Monte Carlo simulation cosRMC input file. The technical solution comprises the following steps: dividing the entire HU value range into 35 segments, each corresponding to a human tissue with different densities, and setting the corresponding elemental composition mass percentages. The present invention converts CT images into a Monte Carlo simulation cosRMC input file. By dividing the HU value range, extracting and utilizing image data, accurately constructing a geometric model, utilizing a repeating structure function, flexibly setting source information and counters, and performing flux-dose conversion, the method achieves precise simulation of human tissue characteristics, efficient data processing, accurate model construction, and comprehensive statistical information. Ultimately, this method facilitates precise dose calculation and provides a strong guarantee for the formulation of BNCT treatment plans.

The invention discloses a back gate dynamic compensation circuit for radiation resistance, and relates to the technical field of total dose radiation resistance, and the back gate dynamic compensation circuit comprises a total dose radiation detection circuit, a dosimeter signal conversion circuit, a signal coding circuit, a digital-to-analog conversion circuit and a compensation voltage generation circuit. The dosimeter signal conversion circuit is respectively connected with the total dose irradiation detection circuit and the signal coding circuit, the digital-to-analog conversion circuit is connected with the signal coding circuit, and the digital-to-analog conversion circuit is also connected with the compensation voltage generation circuit; the total dose irradiation detection circuit is used for carrying out total dose irradiation detection and converting an accumulated dose into a total dose digital signal; the dosimeter signal conversion circuit is used for converting the total dose digital signal into a switching signal; the signal coding circuit is used for converting the switching signal into a corresponding coding signal; the digital-to-analog conversion circuit is used for generating a corresponding reference level according to the coded signal; the compensation voltage generating circuit is used for generating a compensation voltage according to a reference level.

The application discloses a kind of mouse animal cages for radiation experiment, it is related to the technical field of animal cage.It includes accordion variable radian single cage body, the first end of the accordion variable radian single cage body is provided with male door, the second end of the accordion variable radian single cage body is provided with female door, the two sides of the male door are provided with concave slot, the two sides of the female door are provided with gable slot, the concave slot, gable slot inside is provided with isolation insert plate.The metal fence on the top of the mouse cage is replaced by plastic and other materials that do not affect the penetration of the rays;The width of each cage is suitable for holding one mouse (it can be designed to be adjustable, and two widths can also be fixed according to the size of common mice);According to the concentric circle formed by the straight line distance of point source and dose conversion, the radian of the feeding cage can be adjusted, which is consistent with the circumference of the concentric circle, so as to accurately control the dose of irradiation.

The invention provides a medical radiation protection early warning method and device based on personal dose monitoring, and is applied to the technical field of data processing. According to the method, the standardized dose monitoring sequence is generated through multi-source data fusion and adaptive filtering, and then the individualized radiation accumulation model is constructed through Monte Carlo simulation and stratified sampling. On the basis of time-dose dependence characteristics, a linear quadratic model is coupled with a dose rate correction term to construct an evaluation equation, and the key organ absorbed dose is calculated in combination with a dynamic dose conversion matrix. Through data comparison, abnormal signals are identified, damage acceleration factors are defined, health archives are combined for grouping, a random forest algorithm is used for constructing a personalized early warning model, finally graded early warning and protection suggestions are output, and a complete early warning chain is formed.

The present application relates to the technical field of Monte Carlo particle transport calculation and radiation safety analysis in nuclear science, and particularly relates to a method and system for determining shutdown dose rate of nuclear facilities, the method comprising: S1, calculating the generation rate of each photon generated by the decay of each secondary radionuclide and summing up to obtain the total generation rate of all photons corresponding to each collision when each collision occurs; according to the ratio between the generation rate of each photon at each collision and the total generation rate at the collision, sampling photons from all the photons generated at each collision, taking the total generation rate corresponding to each collision as the weight of the sampled photons corresponding to each collision, and performing photon transport calculation to count the photons in the target region, and combining the photon flux-dose conversion factor to obtain the shutdown dose rate distribution of the photons in the target region. The shutdown dose rate can be quickly and accurately calculated to provide accurate data support for subsequent processing of nuclear facilities.

The invention provides a dose conversion method, electronic equipment, a computer readable storage medium, a computer program product and a radiotherapy system. The method comprises the following steps: acquiring first material dose information of particles; obtaining a conversion relation of dose deposition of the particles between the first material and the second material; and converting the first material dosage information of the particles into second material dosage information according to the conversion relation. According to the method, the dose deposition conversion relation of the particles is considered, and the dose information of the particles in different materials is quickly and accurately converted. The conversion method has important application value in (proton, heavy ion and the like) radiotherapy and other radiation dose scenes (such as the field of space radiation dose and the like), can realize comparison and analysis of particle dose in different tissues and media, and provides technical support for optimization and personalization of particle therapy and other radiation dose scenes.