43 results about "Absorbed dose" patented technology

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 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 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 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.

The invention provides multifunctional bioadhesive hydrogel as well as a preparation method and application thereof, and relates to the technical field of biomedical materials. The preparation method comprises the following steps: dissolving dopamine modified gelatin (DA-Gel), sulphobetaine methacrylate (SBMA), acrylic acid (AA) and perfluoroalkyl ethyl methacrylate (PFEMA) in a dimethyl sulfoxide (DMSO) solution, uniformly stirring, injecting into a mold, carrying out cross-linking polymerization by adopting electron beam radiation without adding a chemical cross-linking agent, and preparing a hydrophobic film by adjusting the radiation absorption dose (0-50 kGy) and the hydrophobic monomer content. The mechanical property, the adhesion strength and the swelling behavior of the hydrogel can be accurately regulated and controlled, and the hydrogel with a three-dimensional interpenetrating network structure is obtained. The hydrogel prepared by the process can form rapid and tough adhesion on the surface of a moist tissue, effectively seal a wound, resist swelling in a body fluid environment and promote tissue regeneration, and has a wide clinical application prospect in the fields of wound hemostasis, surgical incision closure, viscera perforation repair and the like.

The present application relates to the technical field of radiotherapy control, and discloses a treatment control method and system for AB-BNCT. The method comprises the following steps: sending a beam-out condition verification request and a beam-out safety verification request in response to a beam-out request; sending a beam-out button display instruction after receiving the pass results, so that the beam-out button is displayed based on a preset state; monitoring main real-time beam data in real time in response to a state change of the beam-out button; determining a main real-time neutron absorption dose based on the main real-time beam data; and sending a beam control instruction to an accelerator based on the main real-time neutron absorption dose and a target neutron absorption dose, so that the accelerator controls the beam in response to the beam control instruction. By comparing the real-time dose with the target dose, the treatment is continued or stopped, and the accuracy of the treatment and the safety of the patient are ensured. The present application solves the technical problems of low safety and dose verification lag in the existing AB-BNCT treatment, and improves the safety and efficiency of AB-BNCT treatment.

The invention discloses a radiation processing quality improvement and risk management and control method based on overall process key parameters, belongs to the technical field of radiation processing quality control, and aims to solve the problem that corresponding process evidences cannot be provided during high-risk and high-quality requirements or overall process tracing of foreign regulations. The method comprises the following steps: carrying out a PQ test, obtaining a reference processing parameter and a reference absorbed dose D0, determining the reference processing parameter according to the type of irradiation equipment, putting a batch of medical products on line, and deploying real-time monitoring equipment. The real-time monitoring equipment is used for capturing key parameter measured values in the machining process according to a preset sampling frequency; according to the invention, through the monitoring granularity leap from batch compliance to single box compliance, it is ensured that the dose received by each box of products is in a strictly controlled range, and the risk of abnormal intermediate product dose caused by process fluctuation in a traditional method is fundamentally avoided; and real-time recording and long-term tracing of whole-process parameters are realized.

The present application relates to a kind of irradiation experimental line mechanism, including walking part and fixed part, walking part includes experimental box, the suspension chain of experimental box top and anchor iron being arranged at the bottom of experimental box are constituted;Fixed part includes the track for the walking of suspension chain, and the limiting anchor rail that is arranged below track and cooperates with anchor iron.Implementation, the experimental box can utilize irradiation device monitoring line to carry out irradiation experiment, provide effective data for small-dose gamma irradiation processing, realize the stable balance of irradiation dose range;For the effective data obtained by experimental box, draw out isodose distribution curve diagram, the index such as the statistics equivalent maximum dose area, equivalent minimum dose area, dose non-uniformity, main control time and absorbed dose relationship, so that production line can carry out small-dose precision irradiation, avoid capacity waste.

The invention discloses a method for evaluating radioactive contamination of a decommissioned uranium mine area based on multi-source data fusion, and relates to the field of uranium mine area governance, and the method comprises the steps: detecting the radon exhalation rate, the radon concentration, the gamma air absorbed dose rate and the radionuclide content in soil of a to-be-evaluated decommissioned uranium mine area; calculating the public radiation dose according to the radon concentration and the gamma air absorption dose rate of the decommissioned uranium mine area; detecting the radioactive element concentration in the surface water of the decommissioned uranium mine area and the radioactive element content in the water sediment; calculating a Nemerow index as a comprehensive pollution index of the surface water based on the concentration of radioactive elements in the surface water; calculating a geocumulative index based on the content of radioactive elements in the water-based sediment as a comprehensive pollution index of the water-based sediment; and performing radioactive pollution assessment on the decommissioned uranium mine area according to the radon exhalation rate of the decommissioned uranium mine area, the public radiation dose, the radionuclide content in the soil and the comprehensive pollution index of the surface water and the water sediment.

The invention relates to the technical field of radiation processing, and discloses a radiation processing control method and system based on the Internet of Things, and the method comprises the steps: converting an operation parameter signal of radiation equipment, deploying a sensor network, and collecting and preprocessing sensor data; a process parameter instruction set is obtained through process knowledge base matching and physical calculation; executing parameter setting and safety interlocking check, and then allowing beam outgoing; calculating a one-way absorbed dose and an accumulated absorbed dose, and performing parameter adjustment and irradiation control according to a calculation result; creating a unique batch traceability code and performing data association, generating an irradiation certificate, and obtaining irradiation batch data; a multi-objective optimization model is constructed, and a production scheduling plan is solved and generated; extracting equipment health characteristic parameters and evaluating health levels to obtain an equipment health evaluation report and a maintenance plan; according to the invention, through real-time dose monitoring and feedback control, process parameters are dynamically adjusted, so that the quality qualification rate of irradiation products is improved.

This invention discloses a voxel-based system and method for determining the equivalent biological dose of targeted alpha nuclide therapy. The system constructs a patient-specific three-dimensional voxel anatomical model and activity distribution map through an image processing module; an intelligent source term module, based on the decay characteristics of the selected alpha nuclide, calls a pre-built dose point kernel database to generate an equivalent total dose point kernel; a dose calculation module performs rapid convolution calculation based on cumulative activity and the equivalent total dose point kernel to obtain the three-dimensional physical absorbed dose; and a biological dose module integrates a micro-dose kinetic model to convert the physical dose into a three-dimensional biological dose distribution map equivalent to conventional external beam radiotherapy. This invention overcomes the technical shortcomings of standard models, such as large errors, time-consuming Monte Carlo simulations, reliance on multi-timepoint dynamic imaging, and the inability of physical dose to reflect the biological effects of alpha particles. It achieves efficient, accurate, and clinically practical individualized biological dose assessment, significantly improving the accuracy and safety of treatment plans.

The invention provides a radiation preparation method and application of zwitter-ion hydrogel, and relates to the technical field of biomedical material preparation, SBMA and MPC monomers are weighed according to the mass ratio of 10: 1-10: 5, dissolved in deionized water and stirred and dissolved under nitrogen protection, a 1MeV electron accelerator is used for radiation, the dosage rate is 5 kGy / pass, the total absorbed dosage is 20 kGy, and a P (SBMA-co-MPC) zwitter-ion prepolymer is prepared; then mixing the prepolymer with PVA (polyvinyl alcohol) and PEGDA (polyethylene glycol diacrylate), heating to 90 DEG C to dissolve the PVA and the PEGDA, pouring into a mold, and carrying out freezing and thawing cycles of freezing at-40 DEG C for 12 hours and unfreezing at room temperature for 4 hours for three times to form a physical cross-linked network, wherein the concentration of the PVA is 2g / 10g water, and the concentration of the PEGDA is 0.2 g / 10g water; and finally, carrying out electron beam radiation crosslinking on the primarily formed hydrogel at a dosage rate of 5 kGy / pass and a total absorption dosage of 20 kGy to obtain the hydrogel with the three-dimensional porous structure. The method is mild in reaction condition and free of pollution, the hydrogel has high mechanical strength and anticoagulation and antibacterial functions, and a reliable material is provided for medical equipment application.

The present invention relates to methods and kits for assessing the absorbed dose of ionizing radiation and the severity of tissue damage from radiation in a patient. It provides the ability to detect erroneously overexposed individuals, select individuals, optimize the schedule of countermeasure doses used for treatment, and monitor the effectiveness of tools for a particular individual.SOLUTION: A multiplex assay kit for use in assessing absorbed doses of ionizing radiation or radiation-induced tissue injury in a patient sample, said kit configured to measure the level of a plurality of biomarkers in said sample, wherein said plurality of biomarkers comprises: (a) DNA damage biomarkers; (b) inflammatory response biomarkers; (c) tissue damage biomarkers; (d) tissue damage repair biomarkers; (e) hematology surrogate markers; and (f) combinations thereof.SELECTED DRAWING: None

The invention relates to the technical field of radiotherapy control, and discloses a treatment control method and system for AB-BNCT. The method comprises the following steps: sending a beam outgoing condition verification request and a beam outgoing security verification request in response to a beam outgoing request; after the passing results are received, a beam-out button display instruction is sent, so that a beam-out button is displayed based on a preset state; monitoring main real-time beam data in real time in response to the state change of the beam output button; determining a main real-time neutron absorption dose based on the main real-time beam data; and sending a beam control instruction to the accelerator based on the main real-time neutron absorption dose and the target neutron absorption dose, so that the accelerator controls the beam in response to the beam control instruction. By comparing the real-time dose with the target dose, the treatment is continued or stopped, so that the treatment accuracy and the patient safety are ensured. According to the invention, the technical problems of low safety, dose verification lag and the like in the existing AB-BNCT treatment are solved, and the safety and efficiency of the AB-BNCT treatment are improved.

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.

This invention discloses a Monte Carlo simulation method and system for iodine-131 drug treatment of thyroid tumors. The method includes: constructing a three-dimensional geometric model simulating radiation transport in a Monte Carlo simulation platform, including a first region model simulating neck soft tissue, a second region model embedded within this model simulating lesions, and a third region model assessing the impact of the radiation environment; configuring the physical processes simulating iodine-131 decay and particle-matter interactions based on the geometric model; defining a particle emission source based on iodine-131 decay data within the second region model; executing the simulation to obtain first energy deposition data for assessing tumor absorbed dose and second energy deposition data for assessing radiation leakage. Compared with existing technologies, this invention constructs a simulation method integrating neck, lesion, and environmental assessments, simultaneously outputting quantitative data on tumor dose and environmental leakage, achieving an intuitive quantitative assessment of the internal distribution and external impacts of the radiation field during iodine-131 treatment.

The invention discloses an adult rat fine eye model and dose calculation method based on Monte Carlo. The method comprises the following steps: acquiring eye structure information of an adult rat; comparing and integrating the structure information and the literature data, and performing experimental verification on data with differences to obtain verified structure parameters; in Monte Carlo simulation software, an adult rat eye three-dimensional geometric model is constructed, and material parameters are set for different eye tissues in the three-dimensional geometric model; setting the type, energy, direction and spatial distribution of an incident particle beam in Monte Carlo simulation software, establishing a coordinate system by taking an eye axis of the three-dimensional geometric model as a reference direction, and executing particle transport and interaction simulation to track the transport process of primary particles and secondary particles thereof in the three-dimensional geometric model; a dose sensitive unit is provided, recording energy deposits within the volume of the lens, and normalizing the energy deposits based on the total mass of the lens to obtain an average absorbed dose of the lens.

The application discloses a kind of simulation prediction methods of indoor radioactivity distribution, comprising: constructing indoor building model, the radioactivity absorption simulation of different radionuclide sources is carried out, and the photon flux of corresponding position in the room of indoor building model is obtained;Calculate the ideal absorption dose rate of room irradiation under the specific activity condition of different radionuclide sources;Photon flux is used as input data, and target absorption dose rate is used as output data;Training data set is constructed, random forest regression model is trained, and trained random forest regression model is output;The photon flux of radionuclide in different positions in the room collected by photon detector is input into trained random forest regression model, and the distribution of indoor room irradiation absorption dose rate is obtained.The application can be used for radioactivity level analysis in multi-target scene, and solve the problem that previous building material radioactivity level analysis can only be calculated by empirical formula, so that it is not accurate enough.

The application discloses an X-ray blood irradiation device calibration device and a calibration method. The calibration device comprises a detector, a detector host and a blood equivalent phantom. According to the target irradiation container, the blood equivalent phantom is selected and placed, the detector is connected with the blood equivalent phantom, the detector is moved to a reference point, the absorbed dose value of the reference point is read to calculate the indication error, the absorbed dose value of each measurement point is read to calculate the absorbed dose uniformity of the target irradiation container, and the reference points of each irradiation container are taken as measurement points, the values read by the detector are used to calculate the consistency of the absorbed dose values among the irradiation containers. The scheme realizes the measurement of dynamic blood irradiation dose, solves the problem that the existing X-ray blood irradiation device cannot accurately measure the irradiation dose and the irradiation dose uniformity, realizes the transmission of data without punching in the measurement chamber, the measurement result can be reproduced, and is more suitable for repeated measurement.

Embodiments of the present specification provide a method and system for determining scanning parameters of photon counting CT and an imaging device. The method comprises: obtaining characteristic information of a target object, the characteristic information comprising at least one of a three-dimensional image containing the target object obtained by an image acquisition device, historical size data of a scanning part of the target object, and body size information of the target object; determining a size of the scanning part of the target object based on the characteristic information; obtaining a constant factor, the constant factor being determined based on a social group related to the target object; determining an absorbed dose corresponding to initial scanning parameters of the target object according to the size of the scanning part and the constant factor; and adjusting the initial scanning parameters of the target object based on the absorbed dose.

This application relates to the field of condiment processing technology and discloses a composite irradiation process for producing fermented broad bean paste. The process includes the following steps: adding water to the fermented base paste to reduce salinity, extracting the clarified liquid, and continuously monitoring the first derivative of the infrared characteristic absorption signal using an ATR-FTIR spectrometer. When the derivative enters a specific range, a concentration program alternating between microwave heating and vacuum flash evaporation is initiated to dehydrate, cool, and restore salinity. Subsequently, an oxygen-containing mixed gas is introduced into the fermented paste, and the spread paste is subjected to 60Co γ-ray penetrating irradiation at 0.0℃ to 4.0℃. Finally, a high-barrier composite material is used for nitrogen-filled deoxygenation packaging. This process uses online infrared monitoring to capture the flavor accumulation equilibrium point, utilizes trace dissolved oxygen to assist radiation sensitization, reduces the number of residual bacteria at a lower absorbed dose, and inhibits the risk of later bag bloating, while simultaneously improving the retention of the original sauce's flavor and physicochemical quality.

To provide a radiotherapy technique that maximizes the absorbed dose in lesion tissue while minimizing the absorbed dose in normal tissue, even if the internal position of the lesion has changed since the treatment planning stage. [Solution] The system includes a storage unit (30) that stores first movement information (31) for moving a tabletop (26) so that a first position (21) of a lesion (15) identified from first voxel data (11) coincides with an isocenter (16) of a beam (20) that administers a dose to the lesion (15), and irradiation conditions (35) for the beam (20) that are set so that the lesion coverage rate of the patient (25) due to irradiation with the beam (20) is maximized at the first position (21); an identification unit (19b) that identifies a second position (22) of the lesion (15) from second voxel data (12) captured immediately before irradiating the beam (20); and an update unit (50) that updates the first movement information (31) to second movement information (32) so that the lesion coverage rate (40) at the position of the lesion (15) of the patient (25) is maximized without changing the irradiation conditions (35).

The application provides a kind of unknown environment radioactive source autonomous search method, device and system, compared with the method currently adopted, not only guarantee the safety of staff, reduce the possibility that radioactive source search personnel is injured by radiation;At the same time, the service life of robot in radiation environment is also considered, the absorbed dose of robot in the process of radioactive source search is reduced, so that the service life of robot can be extended, and the use cost of long-term search of radioactive source of robot is reduced.

The invention discloses a single-energy X-ray air kerma valuing method, and relates to the technical field of ionizing radiation metrology, and the method comprises the following steps: S1, building a standardized single-energy X-ray radiation field through a single-energy X-ray generation device; s2, collecting and analyzing the energy spectrum of the single-energy X-ray through an energy spectrum measurement system, and calculating the absorbed dose rate of the detector; s3, calculating the absorbed dose rate of air according to the absorbed dose rate of the detector; and S4, the air kerma energy is calculated under the electronic balance condition. According to the method provided by the invention, differential correction can be carried out on the energy response characteristics of different types of radiation monitoring equipment, the measurement error after equipment calibration is reduced, and the dose measurement accuracy is improved.

The application discloses a MOS device for nuclear radiation measurement and a preparation process, and relates to the technical field of nuclear radiation measurement, and the device comprises an SOI substrate and an active region; the SOI substrate comprises a silicon substrate, a buried oxygen layer and a top silicon film from bottom to top; the active region is in a mesa structure and comprises a source electrode region, a drain electrode region, a channel region, a metal contact layer and a gate oxide layer; the source electrode and the drain electrode are distributed at two ends of the mesa; the channel region is located between the source electrode and the drain electrode; the upper surface and the outer side of the source electrode and the drain electrode are deposited with the metal contact layer; metal leads are arranged on the metal contact layer and correspond to the positions of the source electrode region and the drain electrode region, so as to realize the electrical connection between the device and an external circuit; the gate oxide layer covers the uppermost layer of the whole active region; contact holes are formed on the gate oxide layer and correspond to the positions of the source electrode region and the drain electrode region; and the contact holes expose the top surface of the metal contact layer. The device and the preparation process can be flexibly integrated into the system on chip of equipment, so that the on-chip accurate measurement of the nuclear radiation absorbed dose can be realized.