333results about "Radiation measurement" patented technology

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 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 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 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 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.

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.

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

To protect a radiation detector from an impact.SOLUTION: A radiography device of the present invention comprises: a radiation detector that converts radiation passing through a subject into an electric signal; a support base that supports the radiation detector, and has a first protrusion part provided on an opposite side relative to a support plane supporting the radiation detector; and an outer sheath that incorporates the radiation detector, and has a second protrusion part provided in a bottom surface facing the first protrusion part. The support base has a third protrusion part provided in a lateral face vertical to the support plane, and a distance between an inner side plane facing the third protrusion part out of the outer sheath and the third protrusion part is more than a distance in a direction vertical to a radiation incidence direction between the first protrusion part and the second protrusion part.SELECTED DRAWING: Figure 4

The invention discloses a liquid-phase deuterium-doped anti-radiation optical fiber, a preparation method and application, and belongs to the technical field of manufacturing of anti-radiation optical fibers. According to the method, deuterium is stably doped into a fiber core in the form of OD groups in the preparation stage of the optical fiber preform through an improved chemical vapor deposition combined solution doping technology, so that the problems that gas is easy to leak and the radiation resistance is attenuated along with time in a traditional gas loading technology are solved. The preparation process comprises the steps of pretreatment of the deposition tube, preparation of the barrier layer and the porous loose layer, solution soaking OD group doping, sintering collapse and wire drawing treatment. An OD group can be detected in the prepared optical fiber, the radiation resistance of the optical fiber is remarkably improved, after the optical fiber is irradiated by gamma rays with the total dose of 200Gy (Si), the radiation-induced attenuation is remarkably lower than that of a common optical fiber without the OD group, and a material basis is provided for long-term reliable application of the optical fiber in radiation environments such as space exploration and nuclear facilities.

The application discloses a kind of separation pretreatment device for radioactive cesium in seawater, belong to seawater separation technical field.The seawater separation cylinder is included, the filter cover for filtering impurities is assembled at the top of seawater separation cylinder, the modular enrichment separation mechanism is configured with the inside circle center position of seawater separation cylinder, modular enrichment separation mechanism is assembled by a plurality of pre-assembled annular frame upward stack, and each pre-assembled annular frame is attached with a plurality of enrichment resin frame by magnetic attraction, to constitute the modular separation enrichment column of seawater separation cylinder circle center end, by the combination of modular enrichment separation mechanism and magnetic attraction, the quick, safe replacement of radioactive cesium adsorption separation end is realized, effectively solve the problem that the whole enrichment column is replaced cumbersome in prior art, long downtime, when some resin frame adsorption saturation, can be individually disassembled and replaced, without stopping or disassembling entire column body, significantly reduce the maintenance time and the radioactive exposure risk of operator.

The application discloses a method and system for quantitatively analyzing self-insulation resistance shunt effect of a self-powered detector, and the design steps are as follows: a circuit model of the self-powered detector is established according to a working principle of the detector; specific parameters of each element in the circuit are calculated according to geometric structure and physical parameters of the detector; a state space equation in a matrix form is established according to a current generation mechanism of the self-powered detector in a radiation field and the circuit model, and a system state transition matrix of the self-powered detector system is established by solving a matrix index; and influences of geometric dimensions and physical parameters of the detector on the insulation resistance and the shunt effect thereof are analyzed according to the system state transition matrix. The method can quantitatively calculate the shunt effect of the insulation layer resistance of the self-powered detector with different structures and parameters, and can accurately calculate a change of a capacitive current with time, thereby providing guidance for design and application of the detector.

The utility model discloses a kind of C-14 samplers, it relates to radioactive material sampling equipment technical field, it includes sampling box and air inlet sampling head, catalytic converter and several sampling bottles are equipped in sampling box, sampling bottle is used to hold gas collection liquid in, bubbler is installed in sampling bottle;Sampling bottle includes side by side arranged first sampling bottle, second sampling bottle, third sampling bottle and fourth sampling bottle;The air inlet end of first sampling bottle is communicated air inlet sampling head, the air outlet end of first sampling bottle is communicated the air inlet end of second sampling bottle;The air outlet end of second sampling bottle is communicated the air inlet end of catalytic converter, the air outlet end of catalytic converter is communicated the air inlet end of third sampling bottle, the air outlet end of third sampling bottle is communicated the air inlet end of fourth sampling bottle, the air outlet end of fourth sampling bottle is communicated with power air pump. By this, the utility model is catalyzed by catalytic converter to gas catalytic conversion, improve the absorption effect of C-14, reduce error, improve the accuracy of detection result.

The present disclosure relates to a radiation detector that detects radiation, the radiation detector including a housing, a detection panel that is included inside the housing and detects radiation, a middle plate that is included inside the housing, is in contact with the detection panel, and supports the detection panel, and a supporting member coupled to the middle plate and supporting the middle plate.

Described herein are particle-driven radiogenomics systems and methods that can be used to identify imaging features for prediction of intratumoral and interstitial nanoparticle distributions in cancers (e.g., in low grade and / or high-grade brain cancers (e.g., gliomas, e.g., primary gliomas)). In certain embodiments, the systems and methods described herein extract and combine quantitative multi-dimensional data generated from structural, functional, and / or metabolic imaging. In certain embodiments, the combined multidimensional data is linked to intratumoral and interstitial nanoparticle distributions. For example, this linked data can be used to determine quantitative functional-metabolic multimodality particle-based imaging features and to predict treatment efficacy. These techniques provide an improved quantitative ability to measure treatment response and determine tumor progressions compared to traditional size-based imaging methods.

The invention relates to a nuclear power plant radiation monitoring system test method and terminal equipment. The method comprises the following steps: establishing communication connection with real equipment; simulating an interaction process with related real equipment according to the spare part to be tested so as to obtain interaction data; determining whether the communication network of the to-be-tested spare part is normal according to the interaction data; when the communication network of the to-be-tested spare part is normal and the to-be-tested spare part is a KRT server, acquiring to-be-tested working data when the to-be-tested spare part is matched with a specified on-site processing display unit; and analyzing the to-be-tested working data to determine the fault condition of the to-be-tested spare part. According to the invention, whether communication networks of spare parts such as an LPDU, a KRT server and a DCS system in a nuclear power plant radiation monitoring system are normal or not can be accurately tested, whether the spare parts of the KRT server have faults or not can be comprehensively and accurately tested, and the safety of a nuclear power plant is improved.

The invention discloses calibration equipment capable of simulating a radiation source, which comprises a mounting seat, a plurality of mounting holes are formed in the mounting seat, the upper end of the mounting seat is in contact with a simulation calibration equipment body, the outer side of the simulation calibration equipment body is fixedly connected with a connecting block, the outer side of the connecting block is slidably sleeved with a connecting seat, and the connecting seat is fixedly connected with the mounting seat. The connecting seat is fixedly connected with the mounting seat, a frame is in contact with the outer side of the simulation calibration equipment body, a dustproof net is arranged in the frame, a handle is fixedly connected to the outer side of the frame, a connecting mechanism is arranged on the connecting seat, and a filtering mechanism is arranged on the frame. The invention relates to calibration equipment capable of simulating a radiation source. The calibration equipment has the characteristics that the simulation calibration equipment is convenient to disassemble, overhaul and maintain, and the operation safety of a simulation system is high.

The utility model relates to the technical field of radiation detection equipment, in particular to a quick disassembly and assembly calibration mechanism for radiation detection equipment, which comprises a base, a support frame, an adjusting ring and a calibration assembly. The calibration assembly comprises a segmentation part, a driving module, a conversion part, a voltage stabilization part, a synchronization module and a distribution module, signal segmentation transmission is achieved through the segmentation part, the driving module and the conversion part are matched to switch calibration areas, the voltage stabilization part guarantees stable output of signals, the synchronization module achieves synchronous adjustment of the signals, and the distribution module evenly distributes the signals. The calibration mechanism can be quickly disassembled and assembled, the calibration efficiency and adaptability are remarkably improved, and the requirements of modern radiation detection equipment for high precision, quick response and flexible adjustment are met.

This invention belongs to the field of calibration testing for space particle detection instruments, and particularly relates to a system and method for reducing the flux of ions entering the calibration payload. The system is positioned between the ion source and the detector, and includes: an ion source baffle, a defocusing module, and a receiving baffle. The ion source baffle allows some ions to pass through through a central opening, reducing the ion flux. The defocusing module defocuses the ions passing through the ion source baffle. The receiving baffle allows some ions to enter the detector through a through-hole, further reducing the ion flux. The three parts of this system work together to achieve an adjustable reduction in ion flux, enabling a high-flux ion source to meet the calibration environment requirements of some particle detection instruments with low-flux ion incident intensity.

The invention discloses a channel gain correction method and system for a multi-channel detector, and relates to the technical field of nuclear radiation detection. The method comprises the following steps: collecting original event data by using a multi-channel detector; energy of all channels triggered by the same event is obtained through action time judgment; calculating the total energy value of each event through the energy of each channel to which each event belongs, counting all events, constructing the total energy spectrum of the channel events, setting an energy screening window according to the position of a photoelectric peak in the total energy spectrum, and reserving the events in the energy screening window as an effective event set; performing channel gain coefficient correction by using an iterative algorithm, and monitoring the energy resolution in real time until convergence; and performing channel-level gain compensation on all original event data by using the finally obtained gain coefficient, and outputting and displaying a corrected energy spectrum and a gain distribution diagram. After gain correction, the energy resolution and the position resolution of the detector can be remarkably improved, and the imaging quality and the quantitative accuracy of the system are improved.