533results about "Radiation measurement" patented technology

The invention relates to the technical field of particle detectors, in particular to a signal acquisition, processing and analysis method and system for a particle detector array, and the method comprises the following steps: segmenting a channel amplitude, marking a stable segment by using a range ratio threshold value, calculating a difference ratio, screening monotonically rising channel marking transition, extracting an earliest excitation channel as a starting point, and carrying out signal processing. And retrieving adjacent channel screening time differences in the window as candidates, and taking the channel with the angle change smaller than a threshold value as a trunk section according to time sequence to generate a path structure. According to the method, the amplitude range of a channel in a fixed period is extracted, a stable signal segment is screened, preliminary signal structuring is completed, a rising trend channel is identified through a difference ratio, the first excitation time is extracted to establish a space starting point index, and path candidates are screened in combination with the time difference of adjacent channels and states. Path trunk segments consistent in direction are extracted through angle change analysis, particle path reconstruction is achieved, multi-dimensional parameters synergistically improve the recognition precision, the analysis capability is enhanced, and the misjudgment rate is reduced.

The invention relates to the technical field of radiation monitoring, in particular to a radioactive foam height nuclear monitoring system and a use method. A radioactive foam height nuclear monitoring system comprises an ionization chamber detector; the collimation shielding module is provided with a containing space, the ionization chamber detector is contained in the containing space, the collimation shielding module is provided with a collimation hole, and particles generated by the self-radiation source can pass through the collimation hole. The invention provides a radioactive foam height nuclear monitoring system and a use method, and aims to solve the problem that a conventional radiation detector is difficult to bear an extremely high radiation environment and affects the detection precision.

The invention provides a batch calibration method and device based on a GE function, and relates to the field of radiation detection. The method comprises the following steps: performing energy calibration on target to-be-detected equipment according to a preset acquisition mode under a standard source, and obtaining first energy spectrum data corresponding to the target to-be-detected equipment based on the energy calibration; performing dead time correction operation on the first energy spectrum data; inputting the first energy spectrum data after the dead time correction into a GE energy spectrum correction model, and outputting second energy spectrum correction data based on the GE energy spectrum correction model; integrating the second energy spectrum correction data based on a polynomial weight function to calculate a dose rate corresponding to the target to-be-detected equipment; and on the basis of the corresponding dosage rate of the to-be-detected equipment, carrying out batch calibration on the plurality of to-be-detected equipment. The problem that the whole calibration process consumes a large amount of time due to the fact that data collection, analysis and calculation of GE function parameters are needed for multiple times in the calibration process of a traditional radiation calibration method is solved.

The invention relates to the technical field of ionization radiation detection, in particular to an ionization chamber detection device, a measurement system and a use method. An ionization chamber detection device comprises: a housing having an accommodation space in which a mixed reaction gas is accommodated; the at least one separating polar plate is arranged in the accommodating space, and the separating polar plate is used for separating the accommodating space into at least two sections of detection cavities; the at least two signal collecting polar plates are respectively arranged in different detection chambers; and the at least two signal transmission lines are respectively connected with different signal collecting polar plates, one end of each signal transmission line is connected with the signal collecting polar plate, and the other end of each signal transmission line extends out of the shell and is suitable for being connected with a data collecting and processing unit. The invention provides an ionization chamber detection device, a measurement system and a use method, and aims to solve the problem that a conventional ionization chamber is generally used for intensity and dose measurement of regional radiation and is not suitable for position sensitive detection of a space smaller than the sensitive volume of the ionization chamber.

The invention discloses a dynamic paper feeding control method for double-probe aerosol monitoring, and relates to the field of environmental monitoring instrument manufacturing. The method comprises the following steps: acquiring a currently set paper feeding mode of the aerosol detection device, and performing paper feeding control on filter paper of the aerosol detection device according to a filter paper target displacement corresponding to the paper feeding mode; acquiring a corresponding real-time accumulated pulse number after the aerosol detection device starts paper feeding control, and stopping paper feeding when a paper feeding stopping condition is met; acquiring the perimeter of the positioning shaft and the number of pulses per circle; real-time displacement is determined according to the perimeter of the positioning shaft, the number of pulses in each circle and the number of real-time accumulated pulses; and correcting the real-time displacement according to the target displacement of the filter paper, and dynamically controlling the filter paper of the aerosol detection device again according to the corrected real-time displacement. According to the invention, actual transportation positioning of the filter paper in different paper feeding modes is considered and correction is carried out, so that huge deviation of the detection efficiency of the monitor and serious distortion of a measurement energy spectrum can be avoided.

To provide a calibration device, medical imaging system and calibration method that allow an operator to easily acquire calibration data for a photon-counting detector.SOLUTION: A calibration device used to acquire calibration data for a photon-counting detector that outputs an electric signal corresponding to photon energy of an incident radiation, includes: a holding unit which holds a first basis material and a second basis material having a larger attenuation coefficient for the radiation than that of the first basis material; and a moving mechanism that moves each of the first basis material and the second basis material between a position inside an irradiation field and a position outside the irradiation field by moving the holding unit in a body axis direction of a subject to which the radiation is applied.SELECTED DRAWING: Figure 3

The invention relates to a radiation contamination simulation detection equipment control method based on an ultraviolet fluorescence signal, which is applied to radiation contamination simulation detection equipment, and the equipment comprises a detection probe. The method comprises the steps that a fluorescence intensity original signal and an ambient light interference signal of a target area are collected, the distance between a detection probe and a target surface is obtained, a fluorescence simulation agent is sprayed on the target area and irradiated by an ultraviolet LED lamp, and the simulation agent is used for emitting fluorescence with the wavelength larger than 450 nm under excitation of ultraviolet light; based on the distance and the ambient light interference signal, performing coupling compensation on the fluorescence intensity original signal; and calculating a radiation simulation value according to the calibration fluorescence intensity signal, and outputting information such as the radiation simulation value, the safety level and the component type. According to the method, through non-radiation simulation agent replacement, signal calibration and multi-dimensional analysis technical means, the safety of radiation detection training is improved, the health threat of a real radioactive source to trainees is eliminated, and the accuracy and the information amount of a detection result are remarkably improved.

The invention discloses a calibration method of photoelectron spectroscopy equipment, and relates to the field of semiconductors. The calibration method comprises the following steps: etching a film sample for the first time; carrying out X-ray bombardment on the etched film sample, and collecting a spectrogram; obtaining an etching thickness according to the current thickness of the etched film sample and the initial thickness of the film sample before etching; according to the etching thickness and the spectrogram, obtaining a relationship between the element content of the film sample and the etching depth so as to determine a first etching rate; etching the film sample with the determined first etching rate for the second time by adopting the same etching condition to obtain a second etching rate; when the first etching rate is the same as the second etching rate, it is judged that etching of the photoelectron spectroscopy equipment is stable, and the first etching rate or the second etching rate is determined as a reference etching rate; and when the first etching rate is different from the second etching rate, determining the second etching rate as a reference etching rate. The problems that an X-ray photoelectron spectrometer is stable in etching rate, poor in accuracy and the like can be solved.

The embodiment of the utility model provides a radiation detector module, a radiation detector and imaging equipment. The radiation detector module comprises a detector circuit board which is provided with a detector element for converting received rays emitted by a radiation source into electric signals, and the detector circuit board is provided with a first positioning hole; the collimator assembly is arranged on a transmission path of the rays and collimates the rays radiated to the detector element, and the collimator assembly is provided with a second positioning hole corresponding to the first positioning hole in position; and the frame supports the detector circuit board and the collimator assembly, the frame is provided with a positioning column, and the positioning column penetrates through the first positioning hole and the second positioning hole. According to the radiation detector module, the difficulty of alignment operation can be reduced, accumulation of alignment errors generated in multiple times of alignment operation is reduced, the alignment precision of all the components is improved, and then the detection precision of the radiation detector module is improved.

Systems and methods are provided for calibrating computed tomography (CT) system. In one example, a method for a computed tomography (CT) system comprises, during a calibration of the CT system, measuring a position of a detector element of a detector array of the CT system using a wire of a wire phantom coupled to a table of the CT system, during a rotational scan performed using the CT system; and during a subsequent scan performed on a subject using the CT system, applying the measured position of the detector element rather than a design target position of the detector element during reconstruction of an image from projection data acquired via the CT system; and displaying the reconstructed image on a display device of the CT system.

The invention relates to the technical field of data calibration, in particular to a neutron fluence response calibration method based on a neutron generator reference radiation field, and the method comprises the steps: collecting a counting rate and a neutron fluence rate at each moment in each monitoring period through a neutron detector and a neutron generator; data of each environmental parameter around the reference radiation field at each moment in each monitoring period are obtained; recording each monitoring period and a plurality of monitoring periods before the monitoring period as historical periods; determining the measurement error of each historical period; obtaining the measurement interference degree of each environmental parameter in each monitoring period; and calculating the scattering interference degree of each environmental parameter in each monitoring period to obtain a calibration counting rate, and carrying out real-time calibration on the neutron fluence response. According to the invention, the interference influence of different environmental factors on the measurement result of the neutron detector can be quantified through dynamic environmental changes, the measurement result of the neutron detector is calibrated in real time, and the measurement accuracy of neutron fluence response is improved.

The invention discloses a muon imaging device, and relates to the technical field of particle detection, the muon imaging device comprises a time projection chamber, the time projection chamber is used for performing three-dimensional track reconstruction on cosmic ray muons incident into the time projection chamber, and an imaging function is realized by reconstructing flux distribution or scattering distribution of the cosmic ray muons; the muon imaging device disclosed by the invention is simple in structure, cost-saving and convenient to use.

The invention discloses a radon gas detector test method and related equipment, and the method comprises the steps: obtaining equipment parameters of a tested radon gas detector, and determining the first test concentration of the tested radon gas detector according to the equipment parameters; determining the test distance of the radon gas detector to be tested according to the first test concentration, wherein the first test concentration is in negative correlation with the test distance; controlling the distance between the americium 241 radioactive source and the detected radon gas detector to meet the test distance, and controlling the americium 241 radioactive source to be turned on; acquiring a plurality of first test data acquired by the signal transceiving module from the radon gas detector to be tested during the starting period of the americium 241 radioactive source, wherein the first test data are electric signal data corresponding to alpha particles generated by the americium 241 radioactive source; and determining a test result of the tested radon gas detector according to the plurality of first test data. By adopting the method provided by the invention, the problem of high detection cost caused by a radon source in a traditional detection method is solved.

The invention provides an electron irradiation dose real-time calibration management method and system, and relates to the technical field of data processing, and the method comprises the steps: collecting real-time dose original data at different positions, and carrying out the mapping processing of the real-time dose original data according to a transmission position and a time parameter, and forming a real-time dose matrix containing spatial distribution characteristics; comparing the dose value of each point location with a preset dose reference threshold value, and generating a dose deviation distribution diagram containing deviation magnitude and deviation position; identifying a local area of which the deviation exceeds a preset deviation threshold range, and generating abnormal dose batch information in combination with the product batch number; extracting a transmission speed parameter, a stacking thickness parameter and an irradiation power parameter of a corresponding batch of products to form a running state parameter set; executing hierarchical calibration processing; carrying out calibration verification processing; according to the invention, the autonomy and accuracy of real-time calibration of the electron irradiation dose are improved.

The invention relates to the technical field of radiation measurement, in particular to a detector calibration device and method in a high-current BNCT mixed field, and the device comprises a front moderation plate, a detector accommodation module, and a detector group. The detector containing module is arranged on one side of the front moderation plate, a plurality of placing holes which are distributed in a circumferential mode are formed in the detector containing module according to a preset radius, the detector group comprises a plurality of detector units, the plurality of detector units are placed in the plurality of placing holes respectively, and the plurality of detector units are arranged in the plurality of placing holes respectively. A gold foil is arranged between the placing hole in the top and the detector unit; and a cadmium-coated gold foil is arranged in the placing hole corresponding to the gold foil mirror image. Therefore, through a double calibration method, low-flux reference calibration and high-flux actual beam correction are combined to improve calibration precision.

The invention discloses a GEO and SSO cross-platform satellite high-energy proton data collaborative calibration method based on a solar proton event, and the method comprises the steps: obtaining high-energy proton observation data and space environment disturbance parameter data of GEO and SSO, and carrying out the preprocessing, and obtaining high-energy proton data, satellite space-time position data and environment parameters of a unified flux type; screening high-energy proton data during the event period according to the sun proton event definition to obtain a plurality of event data sets and grouping the event data sets; performing alignment processing on the screened high-energy proton data of the GEO and the SSO; based on the power law spectrum characteristics of the solar proton event, constructing the energy matching relation of each energy channel of GEO and SSO, and determining the effective energy and energy interval of each energy channel of SSO through point-by-point spectrum fitting and statistical inversion; and recalculating the differential flux of the GEO in a corresponding energy channel by using the calibrated effective energy, establishing a point-by-point scatter matrix of the two types of satellite data, and performing linear fitting and correlation analysis to realize calibration.

To provide systems and methods for calibrating a computed tomography (CT) system.SOLUTION: In one example, a method for a computed tomography (CT) system comprises, during a calibration of the CT system, measuring a position of a detector element of a detector array of the CT system using a wire of a wire phantom coupled to a table of the CT system, during a rotational scan performed using the CT system; during a subsequent scan performed on a subject using the CT system, applying the measured position of the detector element rather than a design target position of the detector element during reconstruction of an image from projection data acquired via the CT system (508); and displaying the reconstructed image on a display device of the CT system (510).SELECTED DRAWING: Figure 5A

A method and system for checking a gauge response is described. The method includes positioning samples with known profiles and uniform compositions between a radiation source and a subset of detectors in a detector array linearly arranged in a first direction. Sample signals are generated by irradiating the samples with radiation from the radiation source and detecting radiation transmitted through the samples and to the subset of detectors. The method includes inputting the sample signals into calibrations for each of the subset of detectors and each of the one or more samples, thereby determining values corresponding to each of the one or more samples and each of the subset of detectors. The method determines if the values corresponding to the one or more samples are consistent with the know values of the samples, and thereby provides an indication as to the state of calibration of the gauge.

The present application relates to a kind of for the radiation protection detection in nuclear magnetic machine room, including: shielding sleeve box, by diamagnetic material is made, for shielding external static magnetic field, its internal cavity shape is adapted according to the shape of the used patrol instrument;Ray detection mesh, set up on shielding sleeve box corresponding to the position of patrol instrument probe, by diamagnetic material is made, allow X or gamma ray to penetrate;Instrument data reading mesh, set up on shielding sleeve box corresponding to the position of patrol instrument display screen, by diamagnetic material is made, allow detection personnel to read data directly visually;The import and export of instrument that can be closed, be set on shielding sleeve box, and be equipped with the sealing cover made of diamagnetic material, for the input and output of patrol instrument, the sealing cover is in closed state when detecting.The present application solves the phenomenon that the radiation diagnosis and treatment machine room adjacent place is the radiation protection detection difficult to implement for nuclear magnetic resonance machine room.

The invention provides an online diagnosis and repair method for a uranium mine gamma ray monitoring device, and the method comprises the steps: determining the respective counting rate correction values of a plurality of detectors based on the current working temperature of the uranium mine gamma ray monitoring device, a preset temperature compensation model, and the counting rate detection values of the plurality of detectors; based on the respective counting rate correction values of the plurality of detectors, the detection efficiency of each detector is determined, and the detection efficiency comprises static detection efficiency and dynamic detection efficiency; and if the detection efficiency of any first detector in the plurality of detectors is deviated from the detection efficiency of a specified second detector in the plurality of detectors, circuit parameters of the first detector are adjusted based on the deviation, so that the detection efficiency of the first detector after the circuit parameters are adjusted is consistent with the detection efficiency of the second detector. According to the technical scheme, the measurement precision and the detection efficiency of the uranium ore gamma ray monitoring device in continuous operation are improved, and the uranium ore sorting energy efficiency is improved.

According to one embodiment, a radiation imaging apparatus includes a sensor panel, a control unit, and a housing that houses the sensor panel and the control unit. The control unit includes: a control substrate that controls readout of a signal from the sensor panel; a mounting member on which the control substrate is mounted; a side plate fixed to the mounting member and having a side wall portion provided with an opening portion; and a connector which is provided on the control board in order to connect the control board and the outside, and which passes through the opening part of the side wall part. The housing is provided with an opening for inserting the control unit into the housing along the second direction.

The utility model discloses a kind of high-purity germanium detector vacuum life measuring device, including vacuum generation module and detection component, detection component is by first detection module and second detection module intercommunication composition, vacuum generation module and detection component intercommunication;First detection module includes first vacuum angle valve, vacuum leak and release gas test chamber and first vacuum gauge;Second detection module includes second vacuum angle valve, getter test chamber, getter sample chamber, second vacuum gauge, fine adjustment valve and high-purity test gas tank;The high-purity germanium detector vacuum life measuring device of this is vacuumized to detection component by vacuum generation module, subsequently detects the leak and release gas amount of high-purity germanium detector by first detection module, and then detects the getter gas suction capacity by second detection module, i. e. The vacuum life of high-purity germanium detector can be detected and calculated;The device can effectively detect the vacuum performance of high-purity germanium detector, provide support for the maintenance of high-purity germanium detector, ensure its detection accuracy.

The utility model provides a radiation field measuring and positioning system and a ray standard measuring system, which can improve the measuring and positioning precision. The radiation field measuring and positioning system comprises three first linear guide rails which are fixed on a floor foundation component and extend along a first horizontal direction, and the extending direction is parallel to the direction of a radiation field wire harness; the moving platform is arranged on the three first linear guide rails through sliding blocks and can move along the first linear guide rails, and two second linear guide rails extending in the second horizontal direction are arranged on the moving platform; the measuring platform is arranged on the second linear guide rail through a sliding block and can move along the second linear guide rail, the floor foundation component comprises three supporting beams extending in the first direction, the three first linear guide rails are fixed to the three supporting beams respectively, and for each first linear guide rail, the first linear guide rail and the second linear guide rail are fixed to the measuring platform. At least two sliding blocks are arranged on the movable platform in the first direction, and a magnetic railing ruler or a grating ruler is arranged on one of the three supporting beams.

METHOD FOR DETERMINING A MINIMUM CRITICALITY ACCIDENT SOURCE TERM The invention relates to a method for determining a minimum criticality accident source term, comprising the following steps: obtaining a number of leaky neutrons or photons DN for a minimum criticality accident by determining a minimum number of fissions Vmin, a minimum average number of fission neutrons Nmin, and a minimum leakage rate of neutrons or photons Dmin from respective devices in an installation; obtaining, based on the number of leaky neutrons or photons DN for the minimum criticality accident and an energy spectrum of the minimum criticality accident source term, a leakage source term corresponding to the minimum criticality accident. [Fig. 1]

The invention relates to the technical field of signal analysis, in particular to equipment and a method for filtering radiation monitoring interference values of a plant area. On the basis of the characteristic that non-Gaussian noise interference generated after power equipment is started and stopped can cause abrupt change of a monitoring radiation signal, calculating an electromagnetic interference index of each local waveform signal; then, based on an electromagnetic interference index, screening out feature local signals which are not interfered by non-Gaussian noise and interference local signals which are possibly interfered by non-Gaussian noise; therefore, the signal abnormal degree of each interference local signal is determined based on the deviation condition between the interference local signal and the feature local signal in the time domain and the frequency domain, and the interference local signal and the feature local signal are screened out according to the signal abnormal degree. The filtering effect of radiation signal filtering through sequential statistical filtering according to normal radiation signals is better.

A radiation imaging device according to one embodiment of the present invention comprises: a detection panel that detects radiation; a support member that supports the detection panel, the support member having a first portion extending along a plane orthogonal to a first direction orthogonal to the detection panel, and a second portion extending from the first portion along the first direction and formed integrally with the first portion; a wiring board to which a signal read out by the detection panel is input from the detection panel; and a housing that accommodates the detection panel, the support member, and the wiring board, and that has side wall members extending along the first direction. The support member is fixed to the housing by screwing the second portion and the side wall members, and the length along the first direction of the second portion is greater than the thickness along the first direction of the first portion.

The utility model relates to a lead shielding chamber sample changing structure which comprises a lead shielding chamber cover, a lead shielding chamber body and a movable lead shielding chamber wall, and the movable lead shielding chamber wall is located on the opening side of the lead shielding chamber body and is in sliding connection with the lead shielding chamber body through a sliding rail to form a lead shielding chamber. Two probes of the high-purity germanium detectors which are oppositely arranged are arranged in the lead shielding chamber, when a sample is replaced, the lead shielding chamber cover is opened, and the movable lead shielding chamber wall and the high-purity germanium detectors fixed with the movable lead shielding chamber wall slide through the hand wheel on the slide rail, so that the distance between the two high-purity germanium detectors is adjusted; according to the structure, low-background and high-efficiency measurement of samples with different sizes can be realized, so that the detection sensitivity of the system is improved.

The invention relates to a method for collecting a sample from a tank body. The method comprises the following steps: mounting an outer tube with an accommodating space and a through hole at the bottom of the tank body along the height direction; inserting an inner tube having a collection space inside and a through portion formed therein into the accommodation space of the outer tube; when a sample is loaded from the top of the tank body, the sample is collected into the collection space through the through hole and the through part; and separating the inner tube in which at least a portion of the collection space is filled with the sample from the outer tube.

To allow tactile recognition of an effective photographic area and the front and back of a radiographic device, and prevent a reduction in the strength of a housing.SOLUTION: A radiographic device 100 comprises: a housing 7 that has an incident face 71 on which radiation is incident, a back face 73 arranged opposite to the incident face 71, and side faces 72 connecting the incident face 71 and the back face 73 to each other; and a radiation detection panel 1 that is accommodated in the housing 7. At least one side face 72 of the side faces 72 of the housing 7 is provided with an incident face-side step part 10a that is arranged in correspondence with an effective photographic area of the radiation detection panel 1 and located on the side of the incident face 71, and a back face-side step part 10b that is located on the side of the back face 73. The incident face-side step part 10a and the back face-side step part 10b have shapes different from each other, and at least one of them has a convex shape.SELECTED DRAWING: Figure 1