13 results about "Dose conversion" patented technology

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.

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.

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 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 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.