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38 results about "Dose conversion" patented technology
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Plastic scintillator doped with neutron-sensitive material lithium and method thereof for measuring thermal neutrons
ActiveCN106324657AEfficient measurementLow costMeasurement with scintillation detectorsLithiumNeutron dose
The invention belongs to the field of radiation measurement, and particularly relates to a plastic scintillator doped with the neutron-sensitive material lithium and a method thereof for measuring thermal neutrons. According to the invention, lithium-contained raw materials are added into the plastic scintillator. The lithium-doped plastic scintillator and a photomultiplier tube are connected and are sealed inside an opaque housing so as to form a probe. The probe is placed in a measurement environment and the nuclear reaction occurs between incident neutrons and the lithium-contained raw materials in the plastic scintillator, so that the materials are in an excited state. During de-excitation, photons are sent out. The number of photons is proportional to the number of incident neutrons. Meanwhile, through recording the electrical impulses semaphore of the photomultiplier tube per unit time, the neutron fluence can be calculated, so that the measurement of the neutron fluence is realized. The neutron fluence is multiplied by a fluence-dose conversion coefficient to obtain the neutron dose equivalent. The plastic scintillator and the method are low in cost, wide in application range and high in detection efficiency.
Owner:CHINA INST FOR RADIATION PROTECTION
Accurate Light-Weight Broad-Energy Neutron Remmeter and use Thereof
ActiveUS20170059723A1Comparable and good neutron dosimetry accuracyComparable and good and sensitivityDosimetersMeasurement with scintillation detectorsThermal neutron captureDose conversion
This invention describes a remmeter that is based on the use of an assembly comprising two or more different-sized hydrogenous moderators, each hydrogenous moderator incorporating a hydrogenous spectroscopic fast neutron detector and a thermal neutron detector in order to provide more accurate neutron dosimetry across a wide range of neutron energies (thermal neutrons to >15 MeV) in a form factor that is lighter than conventional remmeters. The new remmeter utilizes the principle of spectral dosimetry, where the energy or energy distribution of the incident neutrons is first measured and then this energy information (along with the measured fluence) is used to establish the dosimetric quantity using the various fluence-to-dose conversion curves (e.g. H*(10) (ICRP (1997)), NCRP-38 (1971)). Using the method of spectral dosimetry, the large variation in response in these curves as a function of neutron energy (especially over the region 1 keV to 1 MeV) is largely mitigated through the use of the energy and fluence information, and the appropriate fluence-to-dose conversion curve to calculate the dose.
Owner:BUBBLE TECH INDS
Accurate light-weight broad-energy neutron remmeter and use thereof
ActiveUS9939538B2Minimal weightAccurately doneDosimetersMeasurement with scintillation detectorsDosimetry radiationThermal neutron capture
A remmeter includes two or more different-sized hydrogenous moderators, each incorporating a hydrogenous spectroscopic fast neutron detector and a thermal neutron detector to provide more accurate neutron dosimetry across a wide range of neutron energies (thermal neutrons to >15 MeV) in a form factor that is lighter than conventional remmeters. The remmeter utilizes the principle of spectral dosimetry, where the energy or energy distribution of the incident neutrons is first measured and then this energy information (along with the measured fluence) is used to establish the dosimetric quantity using the various fluence-to-dose conversion curves (e.g. H*(10) (ICRP(1997)), NCRP-38(1971)). Using the method of spectral dosimetry, the large variation in response in these curves as a function of neutron energy (especially over the region 1 keV to 1 MeV) is largely mitigated through the use of the energy and fluence information, and the appropriate fluence-to-dose conversion curve to calculate the dose.
Owner:BUBBLE TECH INDS
Nuclear accident source item inversion method and system
ActiveCN109740103AAchieved release rateImprove practicalityNuclear energy generationResourcesDose conversionData assimilation
The invention discloses a nuclear accident source item inversion method and system. The method comprises the steps of data preprocessing, data assimilation and data post-processing. According to the method and the system provided by the invention, the dose conversion coefficient and different radionuclide release shares of each nuclear accident are utilized, so that the practicability of the nuclear accident source item inversion method is realized, and meanwhile, the calculation of the nuclide release rate and the cumulative release amount in an accident is realized.
Owner:CHINA INST FOR RADIATION PROTECTION
Method for calculating short-half-life daughter nucleus bank deposit external irradiation dose of long-lived radioactive nuclide
The invention relates to a method for calculating the short-half-life daughter nucleus bank deposit external irradiation dose of long-lived radioactive nuclide. The method includes the steps of judging a balance relationship built by a mother nucleus and a daughter nucleus according to an emission source item of a liquid effluent of a nuclear facility, determining a radioactivity factor A and a decay constant factor lambda of the daughter nucleus on a deposit site and a surface deposit external irradiation dose conversion factor DCF of the daughter nucleus, and calculating the surface bank deposit external irradiation dose of the deposit site. The method can be used for calculation of various kinds of surface deposit external irradiation caused by discharge of the liquid effluent of the nuclear facility, and solves the technical problem in relevant evaluation calculation in the prior art.
Owner:CHINA NUCLEAR POWER ENG CO LTD
Energy spectrum acquisition-based portable radiation dose measuring device
InactiveCN109932742AThe overall structure is simple and reliableImprove detection efficiencyX-ray spectral distribution measurementDosimetersDigital signal processingRadiation field
The invention relates to the technical field of radiation dose measurement, in particular to an energy spectrum acquisition-based portable radiation dose measuring device, which comprises a CZT detector module, a signal shaping amplifying circuit, a high-speed AD conversion circuit and a digital signal processing module, wherein the CZT detector module is used for converting particle energy information of a to-be-measured radiation field to corresponding electrical signals; the signal shaping amplifying circuit is used for amplifying the amplitude of the electrical signals outputted by the CZTdetector; the high-speed AD conversion circuit is used for continuously sampling pulse signals outputted by the signal shaping amplifying circuit and converting the pulse signals to a digital quantity for being outputted; and the digital signal processing module is used for performing amplitude information extraction and energy spectrum accumulation on the digital signal waveform outputted by thehigh-speed AD conversion circuit, and after energy spectrum accumulation is completed, based on an energy spectrum dose conversion function, the incident particle type and the radiation dose information of the to-be-measured radiation field are calculated and obtained. In comparison with the prior art, the detailed information of the particle type, the energy and the radiation dose of the to-be-measured radiation field can be provided, the circuit structure is simple and reliable, and popularization is convenient.
Owner:苏州笃瑞监测科技有限公司
Plastic scintillator doped with neutron-sensitive material uranium and method thereof for measuring thermal neutrons
ActiveCN106324655AEfficient measurementLow costMeasurement with scintillation detectorsElectrical impulseNuclear reaction
The invention belongs to the field of radiation measurement, and particularly relates to a plastic scintillator doped with the neutron-sensitive material uranium and a method thereof for measuring thermal neutrons. According to the invention, uranium-contained raw materials are added into the plastic scintillator. The uranium-doped plastic scintillator and a photomultiplier tube are connected and are sealed inside an opaque housing so as to form a probe. The probe is placed in a measurement environment and the nuclear reaction occurs between incident neutrons and the uranium-contained raw materials in the plastic scintillator, so that the materials are in an excited state. During de-excitation, photons are sent out. The number of photons is proportional to the number of incident neutrons. Meanwhile, through recording the electrical impulses semaphore of the photomultiplier tube per unit time, the neutron fluence can be calculated, so that the measurement of the neutron fluence is realized. The neutron fluence is multipled by a fluenc-dose conversion coefficient to obtain the neutron dose equivalent. The plastic scintillator and the method are low in cost, wide in application range and high in detection efficiency.
Owner:CHINA INST FOR RADIATION PROTECTION
Method, system, device, and medium for calculating average gland dose of mammography system
InactiveCN109239755AQuick calculationDosimetersRadiation diagnosticsFlat panel detectorDose conversion
The invention discloses a method, a system, a device, and a medium for calculating the average gland dose of a mammography system. The method comprises the steps of: introducing an incident dose lookup table and an air kerma lookup table; obtaining an exposure voltage value KV, a current time product mAs, a gland compression thickness Thinkness, and a distance SID from a flat panel detector to a radiation source; searching a corresponding incident dose value EntranceDose and a corresponding air kerma value HVL from the incident dose lookup table and the air kerma lookup table; determining a dose conversion factor g and a correction factor c of the gland component; determining a correction factor s of the filtered combination; calculating the average gland dose AGD. According to the method,the system, the device, and the medium for calculating the average gland dose of a mammography system, the incident dose value and the air kerma value can be obtained quickly through the lookup tables, and the average gland dose value can be calculated according to the dose conversion factor, the correction factor of the gland component, and the correction factor of the filtered combination, so that the method, the system, the device, and the medium have the characteristics of rapid calculation, can ensure that the total average dosage does not exceed the guidance level, and is suitable for aconventional digital mammography system.
Owner:深圳蓝影医学科技股份有限公司
Calculation method for dose conversion factor of aquatic organism
ActiveCN107391898AQuick calculationAccurate calculationInformaticsSpecial data processing applicationsBiological bodyConversion factor
The invention relates to a calculation method for a dose conversion factor of an aquatic organism. The method comprises the following steps of determining relationships between related parameters of the aquatic organism and the dose conversion factor according to analysis on the dose conversion factor; by utilizing a Monte Carlo method, calculating dose conversion factor values of the related parameters under different irradiation conditions; performing data fitting on the dose conversion factor values by utilizing a fitting formula; performing error analysis on the fitting formula; and obtaining the dose conversion factor of the aquatic organism. By adopting the method, the dose conversion factor can be quickly and accurately calculated out only by considering organism sizes, organism density, incident particle energy and irradiation ways without considering aquatic organism types; and the method does not need to depend on a large amount of databases and is simple and easy.
Owner:CHINA INST FOR RADIATION PROTECTION
Neutron-sensitive substance cadmium-doped plastic scintillator and thermal neutron measurement method thereof
ActiveCN106324658AEfficient measurementLow costMeasurement with scintillation detectorsExcited stateDose conversion
The invention belongs to the radiation measurement field and relates to a neutron-sensitive substance cadmium-doped plastic scintillator and a thermal neutron measurement method thereof. According to the neutron-sensitive substance cadmium-doped plastic scintillator and the thermal neutron measurement method thereof of the invention, a plastic scintillator is doped with a cadmium-containing raw material; the cadmium-doped plastic scintillator is connected with a photomultiplier tube, and the cadmium-doped plastic scintillator and the photomultiplier tube are sealed in an opaque shell, so that a probe can be formed; the probe is arranged in a measurement environment; incoming neutrons and the cadmium-containing raw material in the plastic scintillator are subjected to a nuclear reaction, so that the material is in an excited state; after the material is de-excited, photons are released; the number of the photons is proportional to the number of the incoming neutrons; the quantity of the electric pulse signals of the photomultiplier tube in unit time is recorded, so that the fluence of the neutrons can be obtained, and therefore, the measurement of the fluence of the neutrons can be realized; and the fluence of the neutrons is multiplied by a fluence-dose conversion coefficient, so that the equivalence of the dose of the neutrons can be obtained. The neutron-sensitive substance cadmium-doped plastic scintillator of the invention has the advantages of low cost, wide application range and high detection efficiency.
Owner:CHINA INST FOR RADIATION PROTECTION
3He proportional counter neutron energy response compensation method via perforated cadmium sheet
The invention relates to a 3He proportional counter neutron energy response compensation method via a perforated cadmium sheet, and belongs to the field of radiation measurement. In the existing methods, response of a 3He proportional counter in a low-energy stage is obviously higher than that of a fluence dose conversion curve given by the publication NO. 74 of the International Commission of Radiological Protection (ICRP), and major errors are brought to practical measurement work if compensation is not performed. According to the method, a layer of thin cadmium sheet wraps outside the 3He proportional counter, and a certain number of pores are perforated on the surface of the thin cadmium sheet. With application of the method, low-energy compensation can be realized and response of the 3He proportional counter to low-energy neutrons can be effectively improved.
Owner:CHINA INST FOR RADIATION PROTECTION
Radiation dose rate measurement system and method based on high-purity germanium detector
PendingCN113466915AReduce wasteReduce Radiation RiskX-ray spectral distribution measurementDosimetersNuclear engineeringDose conversion
The invention discloses a radiation dose rate measurement system based on a high-purity germanium detector. The radiation dose rate measurement system comprises a measurement unit, a simulation unit, a comparative analysis unit and a data processing unit, the measurement unit is used for performing an energy spectrum measurement experiment on the energy spectrum of the radiation source to obtain a real energy spectrum of the radiation source; the simulation unit is used for carrying out Monte Carlo simulation on the energy spectrum measurement experiment to obtain a simulation energy spectrum of the radiation source, and the simulation unit also simulates the radiation source under different energies based on the Monte Carlo simulation experiment after parameter optimization to obtain a continuous energy spectrum of the radiation source; the comparative analysis unit is used for comparing and analyzing the real energy spectrum and the simulated energy spectrum, and performing parameter optimization on the Monte Carlo simulation experiment; and the data processing unit is used for performing energy spectrum dose conversion according to the continuous energy spectrum and obtaining the radiation dose rate based on the energy spectrum dose conversion. The energy spectrum-dose conversion function can be accurately obtained by measuring the energy spectrum of the radiation source and combining the Monte Carlo simulation technology, and then the radiation dose rate is obtained.
Owner:INNER MONGOLIA UNIV FOR THE NATITIES
Hard PVC material dose conversion system and method
ActiveCN114282299AOperational intelligenceAvoid wastingGeometric CADImage enhancementDose conversionPolyvinyl chloride
The invention relates to a hard PVC (Polyvinyl Chloride) material dosage conversion system, which comprises a windowsill imaging mechanism for executing an imaging action to a vacant windowsill without a window frame so as to obtain a corresponding vacant imaging picture; the area judging mechanism is used for determining the solid occupied area of the vacant windowsill without the window frame; and the dosage analysis component is used for determining the dosage of the hard PVC material of the window frame required for manufacturing the vacant windowsill without the window frame, wherein the dosage of the hard PVC material is in direct proportion to the entity occupied area. The invention further relates to a hard PVC material dosage conversion method. The hard PVC material dosage conversion system and method are intelligent in operation and wide in application. According to room windowsills with different areas, targeted visual collection and visual analysis can be performed on site to obtain the entity area occupied by the current room windowsill, and the dosage of the hard PVC material which is positively associated with the entity area and is required for manufacturing the windowsill window frame is determined, so that waste of manufacturing materials is avoided.
Owner:江阴市扬名塑业有限公司
Model and method for ocular lens dosimeter calibration
PendingCN112346109AConservative estimateReasonable estimateRadiation measurementOphthalmologyDosimeter
The invention relates to a model and a method for ocular lens dosimeter calibration. The method comprises the steps: 1, building an ocular lens dosimeter scale and test model which is designed into anelliptic cylinder shape; 2, tightly attaching a dosimeter to the surface of the model, and placing the dosimeter at the position, 3 cm away from the long axis, of the left side of the model; 3, irradiating the model by using photon parallel radiation beams, and carrying out various tests, experiments, calibration or analog simulation; and 4, completing testing, experiment, calibration or analog simulation by taking the irradiation true value as the criterion and combining the dose conversion coefficient Hp (3) / Ka of the ocular lens dose equivalent to the air specific release kinetic energy and the dosimeter reading. The structure and the size of the ocular lens dosimeter scale model are closer to the real situation of the human head, the photon absorption and scattering situation of the head can be better reflected, and the ocular lens dosimeter scale model is beneficial to further perfecting eye crystal dose monitoring, evaluation and radiation protection work.
Owner:CHINA INST FOR RADIATION PROTECTION
Air absorption dose rate measurement method based on pulse height spectrum
The embodiment of the invention relates to an air absorption dose rate measurement method based on pulse height spectrum. The method comprises the steps that a terminal device receives a first operation instruction; pulse height spectrum information and background spectrum information are acquired and analyzed, and fluence spectrum data and background fluence spectrum data are generated; the fluence spectrum data comprise track number data and first count data; the background fluence spectrum data comprise second count data; parameter information is acquired, and the parameter information comprises pulse height spectrum measurement time, background pulse height spectrum measurement time, energy slope data, energy slant range data and fluence spectrum dose conversion coefficients; energy data are acquired according to the energy slope data, the energy slant range data and the track number data; first count rate is acquired according to the first count data and the pulse height spectrummeasurement time; second count rate is acquired according to the second count data and the background pulse height spectrum measurement time; and according to the energy data, the first count rate, the second count rate and the fluence spectrum dose conversion coefficients, the air absorption dose rate is acquired.
Owner:NAT INST OF METROLOGY CHINA
The Calculation Method of Collective Dose in Dispersion Accidents of Transporting Radioactive Materials
The invention belongs to the field of risk assessment of radioactive material transportation, and in particular relates to a calculation method for collective dose in radioactive material transportation dispersion accidents. This method fully divides the area of arbitrary shape concerned in the leeward direction in dispersion accidents into at least one regular-shaped sub-area, calculates the average nuclide concentration of each regular-shaped sub-area, and then further calculates the average nuclide concentration of this area, and then According to the parameters such as shielding factor, dose conversion factor, immersion external exposure time, the number of packages released due to damage, the population density of the area and the area of the area, the collective dose of the area is obtained. The area of collective dose considered in this method is arbitrarily shaped, which is closer to the real situation.
Owner:CHINA INST FOR RADIATION PROTECTION
Calculation method of dose conversion factor for aquatic organisms
ActiveCN107391898BQuick calculationAccurate calculationDesign optimisation/simulationInformaticsBiotechnologyBiological body
Owner:CHINA INST FOR RADIATION PROTECTION
Method for measuring neutrons by silver-doped glass
PendingCN109613598ALow costEasy to processMeasurement with scintillation detectorsNeutron doseHigh humidity
The invention provides a method for measuring neutrons by a silver-doped glass. The method comprises the following steps of: reacting a glass scintillator doped a predetermined proportion of silver with incident neutrons, wherein the energy released by the reaction is lost in the glass material, which will cause the nucleus of the glass material to be in an excited state, and a certain amount of photons will be emitted when de-excited; transmitting the optical signal to a photomultiplier tube through the glass, and recording a converted electrical signal; and multiplying the electrical signalby a fluence-dose conversion factor to obtain the neutron dose equivalent. According to the method for measuring neutrons by silver-doped glass, an excellent neutron sensitive material can be providedby doping a certain proportion of silver material in the glass which is low in cost, easy to process, large or small in volume and resistant to acid, alkali and corrosion, the cost of neutron measurements can be reduced, n and [gamma] discrimination ability is high, and the adaptability to harsh environments such as high temperature, high humidity and corrosiveness is good.
Owner:CHINA INST FOR RADIATION PROTECTION
Energy spectrum-dose measuring method and device
PendingCN114740516AImprove energy response issuesFix stability issuesX-ray spectral distribution measurementDosimetersDoses rateDose conversion
The invention provides an energy spectrum-dose measuring method and device, and the method comprises the steps: carrying out the energy calibration of a spectrometer through a standard radioactive source, and obtaining a conversion relation between a channel address and energy; the conversion relation is expressed through scale factors; n ray peaks of radioactive sources with different energies are measured, the energy of the obtained energy spectrum is divided into n regions, and each region at least has a full-energy peak position of one ray; according to the n areas, spectrum collection is carried out on the n radioactive sources, and n net energy spectrums subjected to energy calibration through the calibration factors are obtained; performing dose value measurement on the n radioactive sources in sequence to obtain n dose rates corresponding to the n net energy spectrums; calculating the relationship between the counting rate of the radioactive source in the n areas and the corresponding dose rate; the relation comprises n energy spectrum-dose conversion coefficients, so as to construct an energy spectrum-dose function; and calculating the full-spectrum dose rate according to the dose rate of each current region.
Owner:NAT INST OF METROLOGY CHINA
Method for measuring neutrons of boron-doped glass
PendingCN109613599ALow costEasy to processMeasurement with scintillation detectorsAtomic nucleusPhoton
The invention provides a method for measuring neutrons of boron-doped glass. A glass scintillator mixed with boron of a preset proportion is reacted with an incoming neutron, energy released by the reaction is lost in a glass material to enable a nucleus of the glass material to be in an excited state, and a certain number of photons are emitted during deexcitation; optical signals are transmittedto a photomultiplier tube through the glass, and converted electrical signals are recorded; and neutron dose equivalents are obtained by multiplying the electrical signals by a fluence-dose conversion coefficient. According to the method for measuring the neutrons of the boron-doped glass, based on the low cost, easy processing, changeable size, acid and alkali resistance, and corrosion resistance of the glass, after a certain proportion of boron material is added, a good neutron sensitive material can be provided, the cost of neutron measurement can be decreased, the identifying capability of n and gamma is good, and adaptability to high temperature, high humidity, corrosion, and other harsh environment is good.
Owner:CHINA INST FOR RADIATION PROTECTION
Radiation dose assessment method for animal organs in particle external irradiation experiments
ActiveCN113420491BSolve difficult problems that are difficult to measure directlyImprove convenienceImage analysisDesign optimisation/simulationDose conversionParticle irradiation
The invention relates to the field of radiation protection, and provides a method for evaluating the radiation dose of experimental animal organs by external irradiation of particles. The organ dose conversion factor can be obtained by using the digital model of the experimental animal and the simulation calculation of particle transportation, and then measuring the air kerma to determine the radiation dose of the organ. Assessment; solves the difficult problem of direct measurement of organ dose, and achieves the technical effect of improving the convenience and accuracy of organ dose assessment.
Owner:ACADEMY OF MILITARY MEDICAL SCI
Plastic scintillator doped with neutron-sensitive plutonium and method for measuring thermal neutrons
ActiveCN106324656BEfficient measurementLow costMeasurement with scintillation detectorsExcited stateDose conversion
Owner:CHINA INST FOR RADIATION PROTECTION
Plastic scintillator doped with neutron-sensitive substance cadmium and method for measuring thermal neutrons
ActiveCN106324658BRealize measurementEfficient measurementMeasurement with scintillation detectorsExcited stateDose conversion
Owner:CHINA INST FOR RADIATION PROTECTION
GAN-based method for converting multimodal low-dose CT to high-dose CT
ActiveCN110559009BRealize generationRadiation diagnostic image/data processingComputerised tomographsDose conversionRadiology
The invention discloses a method and system for converting multi-mode low-dose CT into high-dose CT based on a GAN, and a medium. The method comprises the steps: inputting low-dose CT in any mode; performing two-dimensional discrete wavelet transform on the low-dose CT to obtain a plurality of decomposition results; and inputting the low-dose CT and a plurality of decomposition results into a trained encoder in the GAN network, encoding, and decoding the encoding result through a decoder in the GAN network to obtain a corresponding high-dose modal image. The method is based on the wide development of GAN in multi-domain conversion and the decomposition capability of traditional wavelet transform, the low-dose CT and the wavelet transform result are inputted into the trained encoder in theGAN network together for encoding, the encoding result is decoded through the decoder in the GAN network to obtain the corresponding high-dose modal image, and low-dose CT image conversion in any modeis conveniently converted to the high-dose CT image.
Owner:SUN YAT SEN UNIV
Method for measuring neutrons by using gold doped glass
PendingCN109613601ALow costEasy to processMeasurement with scintillation detectorsNeutron doseHigh humidity
The invention provides a method for measuring neutrons by using gold doped glass. The method comprises: reacting a glass scintillator doped with a predetermined proportion of gold with incident neutrons, so that the energy released by the reaction is lost in glass material; making an atomic nucleus of the glass material in an excited state, then emitting a certain number of photons when de excitation; transmitting an optical signal to a photomultiplier tube through the glass, recording a converted electrical signal; multiplying the electrical signal by a fluence-dose conversion coefficient toobtain a neutron dose equivalent. The method can provide an excellent neutron sensitive material after doping a certain proportion of gold material into the glass based on the low cost, easy processing, changeable size, acid and alkali resistance, and corrosion resistance of the glass. Therefore, the method can reduce the cost of neutron measurement, has better n and gamma identification capability, and has good adaptability to severe environments such as high temperature, high humidity, and corrosion.
Owner:CHINA INST FOR RADIATION PROTECTION
Method for calculating collective dose in radioactive substance transport dispersion accident
ActiveCN107977543AInformaticsSpecial data processing applicationsExternal irradiationDose conversion
The invention belongs to the field of risk evaluation of radioactive substance transport, and particularly relates to a method for calculating the collective dose in a radioactive substance transportdispersion accident. The method includes: fully dividing a concerned arbitrarily shaped region in downwind direction in a dispersion accident into at least one regular-shaped sub region; acquiring theaverage nuclide concentration of all the regular-shaped sub regions; further acquiring the average nuclide concentration of the region; and acquiring the collective dose of the region according to parameters such as shielding factors, dose conversion factors, the immersion external irradiation time, the number of damaged packages generating releasing, the population density of the region, and thearea of the region. In the method, the considered region of the collective dose is arbitrary in shape, and is close to the reality situation.
Owner:CHINA INST FOR RADIATION PROTECTION
Method for calculating average glandular dose of mammary gland
The invention belongs to the field of medical detection, and particularly relates to a method, device and equipment for calculating average glandular dose of mammary gland. The average glandular doseof the mammary gland is calculated by acquiring a backscatter factor and combining an exposure tube voltage, a current time product, a backscatter factor, a gland compression thickness of a target mammary gland, a source image distance, a mammary gland average dose conversion factor, a mammary gland component correction factor and a filter combination correction factor, so that whether the currentexposure parameter can generate excessive radiation or not can be more accurately evaluated according to the obtained average glandular dose of the mammary gland.
Owner:HEDY MEDICAL DEVICE CO LTD
Low air kerma measurement method based on proportional counter type secondary standard
The invention discloses a low air kerma rate measurement method based on a proportional counter type secondary standard device. The secondary standard device is composed of a proportional counter, an ultra-low power consumption charge sensitive preamplifier, a pulse discriminator and the like. Counting-dose conversion factor calibration under X and gamma approximate monoenergy ray conditions is completed in a radiation protection X / gamma national standard or secondary standard device laboratory, and a counting-dose conversion factor calibration curve is solved by using counting-dose conversion factor calibration discrete data; a secondary standard device is adopted to measure a count value of a low-dose-rate radiation field at a fixed position under an irradiation condition and a count value of a natural background; and multiplying a value obtained by deducting a natural background count value from a count value under an irradiation condition by a count-dose conversion factor value under a corresponding energy condition or a weighted count-dose conversion factor value under a multi-characteristic energy condition to obtain a low air kerma rate value. According to the invention, the problem of low air kerma rate measurement value traceability of the environmental level dosimeter can be solved.
Owner:中测测试科技有限公司
Radiotherapy dose verification method
ActiveCN114129912AHigh precisionIn line with the actual situationX-ray/gamma-ray/particle-irradiation therapyDose verificationDose conversion
The invention relates to a radiotherapy dose verification method, and belongs to the technical field of dose verification in a radiotherapy process. The method comprises the following steps of: firstly, extracting an original ray gray scale response value on the EPID from a gray scale response value on the EPID, converting the original ray gray scale response value into an original ray flux on the EPID, then reversely calculating an original ray flux value of each point in a die body, then determining a scattered ray flux value in the die body by using a scattering kernel in the die body, and finally, calculating an original ray flux value of each point in the die body. Using the dose conversion factor in the die body to obtain a dose value of a corresponding position; in the prior art, dose conversion is achieved on EPID in a fitting mode, and due to the fact that actual dose absorption of a certain position in the body of a patient in the radiotherapy process is related to the flux of X (gamma) rays penetrating through the position and is not directly related to the flux on the EPID, compared with the prior art, dose conversion factors of the method better conform to the actual physical process, and the dose conversion efficiency is greatly improved. And the precision of the reconstructed dose is higher.
Owner:BEIJING INSTITUTE OF TECHNOLOGYGY
Method for measuring neutrons by mercury-doped glass
PendingCN109613604ALow costEasy to processMeasurement with scintillation detectorsNeutron doseHigh humidity
The invention provides a method for measuring neutrons by a mercury-doped glass. The method comprises the following steps of: reacting a glass scintillator doped a predetermined proportion of mercurywith incident neutrons, wherein the energy released by the reaction is lost in the glass material, which will cause the nucleus of the glass material to be in an excited state, and a certain amount ofphotons will be emitted when de-excited; transmitting the optical signal to a photomultiplier tube through the glass, and recording a converted electrical signal; and multiplying the electrical signal by a fluence-dose conversion factor to obtain the neutron dose equivalent. According to the method for measuring neutrons by the mercury-doped glass, an excellent neutron sensitive material can be provided by doping a certain proportion of mercury material in the glass which is low in cost, easy to process, large or small in volume and resistant to acid, alkali and corrosion, the cost of neutronmeasurements can be reduced, n and [gamma] discrimination ability is high, and the adaptability to harsh environments such as high temperature, high humidity and corrosiveness is good.
Owner:CHINA INST FOR RADIATION PROTECTION
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