44 results about "Absorbed dose radiation" 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.

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 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 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.

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 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 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.

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 invention discloses a system and a method for measuring equivalent biological dose of targeted alpha nuclide therapy based on a voxel model. According to the system, a patient-specific three-dimensional voxel anatomical model and an activity distribution diagram are constructed through an image processing module; the intelligent energy item module calls a pre-established dose point core database according to decay characteristics of the selected alpha nuclide to generate an equivalent total dose point core; the dose calculation module performs fast convolution calculation based on the cumulative activity and the equivalent total dose point kernel to obtain a three-dimensional physical absorbed dose; the biological dose module is integrated with a micro-dose dynamic model and converts physical dose into a three-dimensional biological dose distribution diagram equivalent to conventional external radiation therapy. The technical defects that a standard model is large in error, Monte Carlo simulation consumes time, depends on multi-time-point dynamic imaging, and the physical dose cannot reflect the alpha particle biological effect are overcome, efficient, accurate and clinically practical individualized biological dose evaluation is achieved, and the accuracy and safety of a treatment scheme are remarkably improved.

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.

This invention relates to the field of wastewater treatment, specifically to an apparatus and method for treating wastewater using ionizing radiation. A wastewater treatment apparatus includes: a container for holding wastewater; a spraying component located on the side wall of the container for spraying the wastewater to be treated into the container in a parabolic manner; an electron beam irradiation component for generating an electron beam, which irradiates the parabolic surface of the wastewater to be treated; and a catalyst supporting component for supporting a catalyst; the catalyst supporting component is located in the middle and / or bottom of the container, such that the catalyst is in contact with the parabolic surface and / or with the wastewater at the bottom of the container. The apparatus and method for treating wastewater using ionizing radiation of this invention can significantly alter the absorbed dose distribution in wastewater, improve electron beam energy utilization, while maintaining the degradation rate of pollutants.

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 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.

The invention provides a voxel-level nuclide dose estimation method based on nuclide imaging and computer equipment. Comprising the following steps: acquiring an X-ray structure image and a gamma-ray function image at a single time point or a plurality of time points; segmenting the region of interest to obtain a plurality of sub-regions of interest, and performing region-level partial volume correction on the plurality of sub-regions of interest of the gamma-ray functional image to obtain a corrected gamma-ray functional image; carrying out registration on the corrected gamma ray function image; and performing activity-dose rate conversion on the registration result to obtain a dose rate, 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. According to the method and the device, the influence of partial volume effect on nuclide imaging resolution can be reduced, so that the nuclide image registration precision is improved, and the radionuclide absorbed dose estimation precision 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 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.

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 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.

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 invention belongs to the technical field of optical fiber communication, and particularly relates to an optical fiber transmission loss prediction method and system based on a physical mechanism and data driving, and the method comprises the steps: obtaining a loss value and an X-ray absorbed dose of an optical fiber sample caused by radiation; determining an initial loss model according to the optical fiber radiation damage mechanism, the loss value and the X-ray absorbed dose; optimizing initial loss model parameters by adopting a nonlinear least square method, and establishing a quantitative relation model of the radiation dose and the optical power loss; acquiring an allowable value of the optical fiber sample, inputting the allowable value of the optical fiber sample into the quantitative relation model to calculate a corresponding optical fiber X-ray absorbed dose below the loss allowable value, determining a corresponding X-ray dose rate according to the optical fiber X-ray absorbed dose, and determining industrial CT detection conditions according to the X-ray dose rate. And the specific influence of the radiation dose on the optical fiber transmission performance is quantified. The damage to the performance of the optical fiber is effectively avoided, and the detection accuracy and reliability are ensured.

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.