95 results about "Absorbed dose" patented technology

The invention provides a microdosimetry-based evaluation method for a targeted alpha radionuclide treatment biological effective dose, and the method comprises the steps: carrying out the integration of a time activity curve of alpha radionuclide in an organ, obtaining the cumulative activity, and calculating the physical absorbed dose and dose rate of the organ through Monte Carlo simulation; based on micro-dose Monte Carlo simulation, constructing a micro-dose spectrum of the alpha radionuclide to obtain saturation correction dose average linear energy for representing radiation quality; obtaining biological effect parameters of the alpha radionuclide by fitting saturation correction dose average line energy and cell experiment data by using a micro-dose kinetic model; and evaluating the biological effective dose of the target organ in combination with the physical absorbed dose, the dose rate and the biological effect parameter. According to the method, the problem that a biological effective dose evaluation method is lacked in dose evaluation of targeted alpha radionuclide treatment is solved.

Techniques for deterministic treatment planning for ion beam therapy are disclosed. In an example method, a computing device receives information about a target volume and surrounding anatomy within a patient, each characterized by a depth and set of dimensions. The computing device defines a spatial grid including a first number of steps. The computing device computes, for each step of the spatial grid, a fluence spectrum and a radial distribution based on iterative solutions to the Lagrangian form of the Boltzmann transport equation. The computing device computes corrections to the fluence spectra based on nuclear interactions. The computing device then determines an absorbed dose distribution to the target volume and the surrounding anatomy and generates an ion beam therapy treatment plan based on the absorbed dose distribution.

The invention discloses a single-bond polymer irradiation damage calculation method, device, equipment and medium, and relates to the technical field of polymer irradiation damage calculation, and the method comprises the following steps: determining the microscopic section type of gamma ray and single-bond polymer; the irradiation damage of the gamma ray to the single-bond polymer is equivalent to the action probability of the gamma ray to the covalent bond; according to the bond forming structure data of the different covalent bonds, the bond breaking probability of the gamma ray to the different covalent bonds is obtained; and obtaining the initial free radical concentration according to the total deposition energy and the bond breaking probabilities of different covalent bonds. According to the method, the action probability of gamma rays on extranuclear electrons of nuclide atoms forming covalent bonds in the single-bond polymer is established, distribution of irradiation damage of the gamma rays in the polymer on various covalent bonds can be calculated, and the probability of covalent bond breaking caused by the irradiation damage can be accurately calculated; and the quantitative relation between the free radical concentration and the material absorbed dose is obtained.

According to the invention, the clinical dose is accurately evaluated. The dose evaluation method includes: a calculation information acquisition step (S1) for acquiring calculation object information including: information relating to radiation including a dose or a dose rate of the radiation to be irradiated to an irradiation object; and information pertaining to the type of cells constituting the irradiation target that is irradiated with the radiation, the information pertaining to the type of cells constituting the irradiation target. An absorbed dose acquisition step (S2) for acquiring, for each type of cells constituting the irradiation target, an absorbed dose indicating the energy of the radiation absorbed by the type of cells; and a calculation step (S4) for calculating, on the basis of the calculation object information and the absorbed dose information, a clinical dose to be irradiated to the irradiation object for each type of cells.

The invention discloses a method and system for detecting environment low-dose ionizing radiation, and belongs to the technical field of radiation detection.The method comprises the steps that house indoor data and building material ionizing radiation parameters are obtained, and an indoor radon concentration change model and a gamma radiation air absorbed dose rate change model are constructed; introducing the measured indoor radon concentration, gamma radiation air absorbed dose rate and indoor building material ionizing radiation parameters into an indoor radon concentration change model and a gamma radiation air absorbed dose rate change model to evaluate the future ionizing radiation condition, and constructing an effective dose evaluation model; indoor radon gas concentration, gamma radiation air absorbed dose rate and resident habits are introduced into an effective dose evaluation model to evaluate the influence of ionizing radiation on residents, an effective dose early warning model is constructed, and the daily total effective dose of ionizing radiation is introduced into the effective dose early warning model to evaluate the safety of ionizing radiation. According to the invention, the influence of the effective dose of ionizing radiation on residents is comprehensively evaluated in combination with resident habits.

The invention discloses a laser therapeutic instrument control method, equipment, a product and a medium, and relates to the technical field of medical instrument control. According to the method, an action area is divided into a plurality of operation units, and a reflection spectrum and a scattering spectrum of each operation unit are acquired in real time by utilizing a detection light beam, so that optical characteristic information of the tissue is accurately obtained; extracting multi-dimensional absorption characteristic parameters including a wave band absorption coefficient, a scattering attenuation coefficient and an effective penetration depth; a dose response function constructed based on the parameters can accurately represent a nonlinear mapping relation between the input laser energy and the actual absorbed dose; differential laser input parameters are reversely calculated through dose equalization processing, so that operation units with different optical characteristics can receive corresponding target absorbed doses; and finally, the laser therapeutic instrument executes operation according to the differentiated parameters, so that accurate energy control on areas with different optical characteristics is realized, and the effectiveness of laser treatment is improved.

This application proposes methods for synthesizing aromatic compounds using ionizing radiation based on N₂O, and methods for synthesizing aromatic compounds using industrial waste gas. The method includes: placing benzene and a combined gas containing N₂O in a sealed container, and adjusting the volume of the combined gas to bring the benzene in the sealed container to its saturated vapor pressure; irradiating the sealed container with radiation to cause the benzene to react and yield the aromatic compounds, wherein the radiation includes X-rays, gamma rays, or electron beams, the energy range of which is 0.0110 MeV, and the absorbed dose rate is 0.1 Gy / min to 1000 kGy / min. This method can synthesize aromatic compounds such as phenol in one step using ionizing radiation based on N₂O without the use of a catalyst, achieving precise and high-value utilization of N₂O.

The invention discloses a carbon ion radiotherapy biological dose modulation system and method based on energy transfer linear density threshold triggering, and relates to the technical field of tumor radiotherapy, and the system comprises an image and target region data import module, an energy transfer linear density calculation module, a dual-model optimization engine module, and a dose verification module. According to the method, a double-model regional optimization framework with specific energy transfer linear density as a physical threshold value is initiated for the first time, a local effect model is taken as an example, the maximum relative biological effect of a low-energy transfer linear density region is adjusted by introducing a modulation factor, the absorbed dose is deduced by combining a corrected local effect model equation, and the energy transfer linear density is calculated. The method realizes accurate improvement of the biological weighted dose of the region, is compatible with a mainstream relative biological effect model, can guarantee the safety of the high-energy-transfer linear density region and the endangered organ dose only through software upgrading, guarantees accurate calculation of the energy-transfer linear density through standard water model experiment calibration, and is suitable for carbon ion radiotherapy of various hypoxia tumors.

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 the technical field of biological material preparation, in particular to a method for preparing carboxymethyl chitosan through irradiation treatment of chitin-enriched biomass and application. According to the method, chitin-enriched biomass is taken as a raw material and is sequentially subjected to pretreatment, irradiation pretreatment, decalcification treatment, degreasing and deproteinization, deacetylation and carboxymethylation; the irradiation absorbed dose of the irradiation pretreatment is greater than 0 and less than or equal to 1000kGy. According to the method, the structure porosity of chitin is improved through high-energy ray irradiation treatment, the permeation efficiency of subsequent reactions such as decalcification and deproteinization is remarkably improved, meanwhile, the dosage of chemical reagents is reduced, and the substitution degree and water solubility of the product are improved by further combining a multi-step synergistic chemical modification process such as freezing alkalization and gradient dialysis purification technologies; the molecular weight distribution is uniform. The high-purity carboxymethyl chitosan provides technical guarantee for development of novel medical materials.

The invention discloses a method for measuring intraoperative radiotherapy Intrabeam water absorbed dose based on air kerma. The method comprises the following steps: characterizing a spectrum; a radiation substance matched with or close to the spectrum is selected, and the energy spectrum of the radiation substance is represented; acquiring measurement parameters of the air kerma rate; calculating a first correction factor by adopting a Monte Carlo method; calculating a second correction factor based on ionization chamber rod scattering; creating a conversion factor from air kerma energy to 1cm water absorbed dose at the measurement point; and calculating the water absorption dose rate at the position of 1cm. The active measurement method is adopted, the ionization chamber is used for measuring the absorbed dose of the rays generated by the spherical source applicator in water, namely the measured value is the absorbed dose at the position of 1 cm in water, the advantages of being easy to operate and short in measurement time are achieved, real-time reading can be achieved, and waiting is not needed.

The application provides a kind of based on deep learning's absorbed dose prediction method, device, equipment and medium, it is related to medical image processing technical field, comprising: obtaining the treatment of patient's pre-test multi-modal data;According to clinical examination data and the mask map of the target tumor region and normal key organ region of pre-set drug, space coding is carried out, and the biomarker feature map of the patient to be tested is constructed;According to the pre-treatment medical image and biomarker feature map, a preset first deep learning model is used for prediction, to generate the simulated treatment initial medical image of the patient to be tested;According to the simulated treatment initial medical image, a preset second deep learning model is used for prediction, to generate the post-treatment predicted dosimetry parameter map of the patient to be tested.The application can improve the accuracy of nuclide absorbed dose prediction evaluation.

The invention discloses an energy spectrum measurement device and method for tough-induced radiation X-rays, and relates to the field of ray detection and measurement, and the device comprises a collimator, a shielding body, a multi-layer absorption measurement assembly and a processor. An X-ray collimation hole channel is formed in the collimator; the shielding body and the collimator are coaxially mounted; a mounting hole channel is formed in the shielding body; the multi-layer absorption measurement assembly is arranged in the mounting hole channel of the shielding body; the multi-layer absorption measurement assembly comprises a plurality of absorption sheets and a plurality of Si dosage sheets which are sequentially arranged at intervals; after electron beam tough radiation X-rays pass through the X-ray collimation hole channel of the collimator, X-ray irradiation is carried out on the multi-layer absorption measurement assembly in the mounting hole channel of the shielding body; the processor is used for determining the energy spectrum data of the electron beam tough radiation X-ray according to the X-ray absorbed dose of each Si dose sheet. According to the invention, the measurement of the electron beam tough-induced radiation MeV wide-energy-region X-ray energy spectrum is realized.

The present invention provides a method, terminal and medium for obtaining a relative total biological effect value based on a boron neutron reaction. The method comprises obtaining a cell survival fraction model and a reference model corresponding to each target depth; obtaining, for each target depth, a mixed absorbed dose and a reference absorbed dose corresponding to the cell survival fraction to be measured according to the cell survival fraction to be measured; and obtaining a relative total biological effect value of the mixed absorbed dose at the corresponding target depth based on the mixed absorbed dose and the reference absorbed dose corresponding to each target depth. The present invention improves the accuracy of obtaining the cell survival fraction model while effectively improving the accuracy of obtaining the relative total biological effect value.

This invention discloses a miniature extrapolation ionization chamber and method for measuring the surface absorbed dose rate of a β-adhesive patch, relating to the field of dose rate technology. The ionization chamber includes a front end and a shell. A micrometer's rotating handle is located at the rear end of the shell, and a micrometer screw extends into the shell. The front end includes an entrance window, which is fixed to the front end face of the shell by a tissue equivalent material pad. A protective ring is disposed around a collecting electrode, which is coaxially positioned inside the shell, with its rear end connected to the front end of the micrometer screw. An insulating gap is formed between the collecting electrode and the protective ring. The entrance window, collecting electrode, and protective ring together constrain the formation of a sensitive volume. The depth of the sensitive volume is changed by adjusting the distance between the collecting electrode and the entrance window using the micrometer. The ionization chamber and method provided by this invention can quickly and effectively calibrate and measure the surface absorbed dose rate of small-area β-adhesive patches.

An object of the present invention is to provide a disposable pipette capable of avoiding mixing foreign matter into a sample. The disposable pipette of the present invention is a disposable pipette (1) used in a medical field or a biochemical field, and includes a resin-made pipette main body (20) having a connection portion (23) connected to a suction device, and a resin filter (30) inserted into the connection portion (23). In the resin filter (30), an elution amount, in a case where the resin filter (30) is subjected to radiation exposure such that an absorbed dose is 20 kGy or more, is equivalent to a maximum absorbance of 0.08 or less in a wavelength range of 220 nm to 241 nm and is equivalent to a maximum absorbance of 0.05 or less in a wavelength range of 241 nm to 350 nm.

The present invention discloses a measuring system and method for measuring water absorbed dose based on ultrasonic temperature measurement technology, including a water tank, a magnetic stirring device, a temperature sensor, a data collector and a hydroacoustic transducer, wherein a magnetic stirring device is arranged at the bottom of the water tank, a plurality of temperature sensors are arranged in the water tank to detect the temperature of different areas, the output end of the temperature sensor is connected to the data collector, a radiation source is arranged above the water tank, and the output end of the hydroacoustic transducer is connected to the input end of the ultrasonic signal emission and collection system. Compared with the calorimetric method, the present invention eliminates the non-aqueous materials in the water body membrane to reduce the complexity of the heat exchange problem, the present invention can perform real-time dose measurement, and the measurement process is relatively simple and the measuring device is light.

To provide an optical glass that has light transmittance of a visible region which is required as an optical glass, and has less reduction of light transmittance in a visible region even in the case the glass is irradiated with radiation.SOLUTION: An optical glass contains, in terms of oxide-based mass%, SiO2 component by 0 to 35%, GeO2 component by 0 to 15%, B2O3 component by 0 to 12%, P2O5 component by 0 to 35%, Nb2O5 component by 5 to 60%, TiO2 component by 0 to 35%, Ta2O5 component by 0 to 10%, WO3 component by 0 to 8%, Bi2O3 component by 0 to 5%, ZrO2 component by 0 to 10%, La2O3+Y2O3+Gd2O3 component by 0 to 45%, Sb2O3 component by 0 to 1%, and Rn2O component by 0 to 25% (note that Rn is one or more kinds selected from Li, Na and K). When the glass receives irradiation of cobalt 60 gamma ray such that an absorption dose becomes 100 krad, transmittance reduction at 450 nm and 550 nm before / after the irradiation is 30% or less.SELECTED DRAWING: Figure 1

The present invention discloses an ionizing radiation dosimeter made of a polymer structural color material and a dose reading method thereof. The present invention utilizes the cracking or cross-linking phenomenon of polymer microstructure materials with characteristic dimensions between 100 nm and 1000 nm under ionizing radiation. This phenomenon causes the characteristic wavelength of the structural color to shift after exposure to a specific dose of ionizing radiation, thereby measuring the absorbed dose of ionizing radiation. Furthermore, the present invention employs standard color card comparison, reflection spectrum measurement, and digital photography hue reading as dose reading methods. The present dosimeter is simple to manufacture, low in cost, has adjustable sensitivity, and can cover the entire visible light wavelength range. Compared with traditional color-changing dosimeters, it uses the wavelength and hue of reflected light, rather than brightness, transparency, or saturation, to measure absorbed dose, offering significant advantages.

Neutron-induced radiation detectors (NiRDs) and radiation dosimetry systems containing the same are described. Examples of NiRDs can include numerous components based on location, function, dimension, and / or constituent materials. A NiRD can be configured to directly measure an absorbed dose (or rate) of particular ionizing reaction products induced by neutrons. The NiRD can utilize various detection schemes for measuring the deposited energy of the reaction products, such as gaseous ionization, semiconducting, scintillating, or homogenous versions of these detection schemes. The NiRD can measure the deposited energy of the reaction products in forward emission, backward emission, or both. Examples of radiation dosimetry systems can include one or more NiRDs, a gamma ray detector, and readout electronics coupled to each of the radiation detectors. Example implementations of the radiation dosimetry systems are described for determining an equivalent dose (or rate) of a neutron beam generated for boron neutron capture therapy (BNCT).

The invention discloses an ionization chamber control method and device, and the method comprises the steps: calibrating the positioning distance of measurement equipment when the ionization chamber is in a connection state with the measurement equipment, carrying out the electric leakage measurement of the ionization chamber in the calibrated measurement equipment, guaranteeing that the ionization chamber meets the measurement standard, and carrying out the electric leakage measurement of the ionization chamber under the condition that the ionization chamber meets the measurement standard. And the ionization chamber is controlled by an automatic measurement program to automatically measure the water absorbed dose of the particle source.

The present invention relates to a method for generating an analog spectrum of a tissue equivalent proportional counter and its application. By collecting the data measured by tissue equivalent proportional counters in the environments of the International Space Station, monoenergetic particles, γ fields, and neutron fields published at home and abroad, and processing the collected data to form a basic spectrum, an analog spectrum that satisfies the measurement distribution law of tissue equivalent proportional counters in the above different radiation fields is generated on the basis of the basic spectrum, and the quality factor Q, absorbed dose D, and dose equivalent H values are obtained from this spectrum, which can be applied to calibrating the hardware measurement system and signal processing module of the tissue equivalent proportional counter. The tissue equivalent proportional counter calibration method disclosed by the present invention has the advantages of high calibration efficiency, real-time calibration, and wide application range.

The application provides a voxel-level radionuclide dose estimation method based on radionuclide imaging and a computer device. The method comprises the following steps: acquiring X-ray structural images and gamma-ray functional images at a single time point or multiple time points; segmenting a region of interest to obtain multiple sub-regions of interest; performing regional partial volume correction on the multiple sub-regions of interest of the gamma-ray functional images to obtain corrected gamma-ray functional images; performing registration on the corrected gamma-ray functional images; performing activity-dose rate conversion on the registration results to obtain a dose rate, and performing voxel-level curve fitting and integration on the dose rate to obtain an absorbed dose distribution result, and determining the absorbed dose of each sub-region of interest based on the absorbed dose result. The application can reduce the influence of the partial volume effect on the resolution of radionuclide imaging, improve the accuracy of radionuclide image registration, and further improve the accuracy of radionuclide absorbed dose estimation.

The application discloses a variable-position large-angle proton irradiation sample table in a vacuum environment, which comprises a sample table arranged in an electronic comprehensive irradiation cabin, and the sample table comprises a motion turntable, a driving mechanism, a transmission shaft, a spline hollow shaft and a spline shaft. One end of the transmission shaft is in transmission connection with the driving mechanism, a fluid sealing device is rotatably sleeved on the transmission shaft, a first universal joint is connected to the fluid sealing device, the first universal joint is hinged to one end of the spline hollow shaft, the other end of the spline hollow shaft is slidably provided with the spline shaft, and the other end of the spline shaft away from the spline hollow shaft is hinged to a second universal joint. The motion turntable comprises a platform base, the platform base is rotatably provided with an X-direction turntable, an irradiation table is rotatably connected to the X-direction turntable through a turntable shaft, and one end of the second universal joint away from the spline hollow shaft is connected to the turntable shaft. When the sample receives the radiation, the uniformity of the absorbed dose of the irradiated object is maximally improved, and the irradiation source can be directly faced.

The present disclosure relates to a method of measuring an absorbed dose of radiation in small irradiation fields. The method of measuring an absorbed dose of radiation in small irradiation fields, includes an acquisition step of acquiring absorbed dose distribution data of radiation; a determination step of determining a region where an absorbed dose of radiation of a predetermined ratio or more is absorbed based on the absorbed dose distribution data of radiation; a formation step of forming a scintillator having a shape in which a plurality of hexahedral cells are coupled to have a shape matching the region; a measurement step of measuring a absorbed dose of radiation irradiating the scintillator from a radiation irradiation device; and a calculation step of calculating the absorbed dose of radiation of the cell at a predetermined position by using predetermined Equations.

The application discloses a kind of for plant seed neutron irradiation 241 Am- 9 Be source dose distribution irradiation device mainly includes cylindrical shield, transport plate, 241 Am- 9 Be neutron source, spherical shielding layer, rubber stick and sample irradiation area;The neutron source will be accompanied by a large number of 59.5keV, 4.438MeV gamma ray production while spontaneous fission, by wrapping spherical lead layer around neutron source shielding gamma ray, so that the main plant seed radiation effect comes from neutron radiation, while the geometric center of neutron source is the spherical center, set up sample irradiation area, ensure the uniformity of plant seed absorbed dose in each area, and directly given without going through tedious measurement and calculation, with the characteristics of standardization dose distribution, can meet the scientific research needs of most legume plant seed neutron irradiation, and can be applied to other kinds of plant seed irradiation and neutron radiation agricultural production and mutation breeding.

The invention relates to the field of electromagnetic radiation detection, and discloses an electromagnetic radiation absorbed dose detection circuit and method and a portable device, the electromagnetic radiation absorbed dose detection circuit is provided with an electric field voltage conversion module, a low-pass filtering module, a resistance transmission line and a broadband signal receiver which are connected in sequence, and the electric field voltage conversion module is connected with the broadband signal receiver through three sub-conversion modules arranged in a three-dimensional orthogonal structure; three-axis component electric field signals are collected in a radar near field and converted into a plurality of corresponding component voltage signals, each component voltage signal is input into a low-pass filtering module to be filtered, each filtered voltage signal is obtained and sent to a broadband signal receiver through a resistance transmission line to be subjected to electric field calculation, and the electric field is calculated. The corresponding human body electromagnetic exposure specific absorption rate is obtained. According to the invention, the detection of the electromagnetic exposure specific absorption rate of the human body can be effectively realized, the detection precision of the specific absorption rate can be effectively guaranteed, and the detection modes of the electromagnetic exposure specific absorption rate of the human body in a radar near field are diversified.

The invention belongs to the technical field of medical radioactive isotopes, and particularly relates to an irradiation-resistant separation material for thorium-barium separation and a preparation method of the irradiation-resistant separation material. The preparation method comprises the following steps: preparing an active material; preparing a polyacrylonitrile matrix; preparing a composite material precursor solution; and molding the composite material. The prepared separation material has good thorium-barium separation performance, can tolerate irradiation with an absorbed dose of 300 kGy, and can be used for preparing an irradiation-resistant 228Th-224Ra generator.

The application discloses a method for preparing a perovskite material rich in oxygen defects by ionizing radiation. The method comprises the following steps: weighing a certain amount of perovskite oxide material, dispersing the perovskite oxide material in a mixed solution of a hydroxyl shielding agent and deionized water, transferring the perovskite oxide material to a test tube after ultrasonic dispersion, sealing the test tube after oxygen removal by blowing in inert gas, and placing the test tube near an ionizing radiation source to prepare a perovskite material rich in oxygen defects. The ionizing radiation source used in the application includes one or more of a gamma ray source, a high-energy X-ray source, an accelerator source and a nuclear waste or space radiation source. The reaction is carried out at normal temperature and pressure, the process is simple, controllable, the content of oxygen defects introduced in the catalyst is adjusted by adjusting the absorbed dose, the whole process is green and environmentally friendly, has significant industrialization advantages, and is expected to be used for large-scale preparation of perovskite materials rich in oxygen defects, and has a wide application prospect in the industrial field.

This disclosure relates to a method for determining bioeffective dose, wherein the method includes: detecting the boron concentration C of each voxel in the target at multiple time points. B ; Calculate C B The corresponding biological effect value (RBE) B Determine C B and RBE B The first association relationship, based on the first association relationship, determines the connection through C. B Characterized RBE B ; Calculate C B The corresponding first physical absorbed dose rate D B And other physical absorbed dose rates corresponding to dose components other than boron, and physical dose rate distribution D phy According to RBE B and D B The product of the other dose components and the product of other biological effect values ​​and other physically absorbed dose rates is used to calculate C. B The combined biological effect value (CBE); based on CBE and D phy Calculate the biologically effective dose D bio According to this disclosure, it is beneficial to determine the appropriate irradiation time for different voxels during BNCT in order to obtain better therapeutic effects.