228 results about "Dosimeter" patented technology

Disclosed is a method for spectrally unmixing spectral data originating from a set of spectral sources and including a series of one or more optical spectra. The method can include modeling the spectral data using an endmember matrix and an abundance matrix, the endmember matrix including a set of endmember spectra respectively corresponding to the set of spectral sources, and the abundance matrix indicates an abundance of each endmember spectrum in each spectrum. The method can also include providing external prior spectral information comprising prior endmember information and prior abundance information conveying at least partial prior knowledge about the endmember matrix and the abundance matrix, respectively, and performing a spectral unmixing operation on the spectral data to determine a solution for the endmember and abundance matrices, using the external prior spectral information as input. The method can be employed for calibrating spectral detection systems such as scintillator-based fiber dosimeters.

The invention discloses a personal dosimeter capable of nuclide identification, and the dosimeter comprises a scintillation detector which is composed of a scintillation crystal and SiPM and captures an energy spectrum signal of a ray; the signal amplifier receives the voltage signal output by the SiPM and preprocesses and amplifies the voltage signal; the multichannel analyzer is used for receiving the amplified signal output by the signal amplifier and realizing energy spectrum acquisition in a target energy range; and the MCU receives the signals acquired by the multichannel analyzer and performs energy spectrum analysis. According to the invention, the scintillation detector based on SiPM and scintillation crystals is used, so that the small size and high sensitivity of the personal dosimeter are realized; according to the multi-channel analyzer, the multi-channel analyzer capable of setting the energy range is realized through the ADC and the comparator, and the design of a peripheral circuit is extremely simplified; the simplified nuclide identification method is designed based on prior information, the range of a nuclide library is narrowed, and the requirements of nuclide identification in a specified application scene for the computing power of a system and the complexity of an analog circuit are further reduced.

The utility model discloses a tool for rapid detection of an irradiation chemical dosimeter, which comprises a bottom plate, two sides of the bottom plate are provided with vertical plates, two fixing plates are arranged between the two vertical plates, one side of each fixing plate is provided with a plurality of test tube fixing holes which are arranged at equal intervals, test tubes are inserted into the test tube fixing holes, and the test tubes are fixed on the bottom plate. A plurality of cuvette fixing holes which are distributed at equal intervals are formed in one side, far away from the test tube fixing hole, of the fixing plate, cuvettes are arranged in the cuvette fixing holes, a cover plate is arranged above the cuvettes, a sealing block is arranged below the cover plate, two convex blocks are arranged on each of two sides of the sealing block, and clamping grooves matched with the convex blocks are formed in the inner walls of the cuvettes. The tool can rapidly detect the irradiation dose of the stoichiometric agent after irradiation, and the dose meter after irradiation is directly put into the spectrophotometer, so that the operation is extremely simple and convenient, the subsequent pipetting operation is not needed, the operation error is reduced, and the accuracy and consistency of the detection result are ensured.

The utility model discloses a dosage box, which comprises a shell and a dosimeter card, wherein the shell is provided with a hollow cavity, and one end of the hollow cavity penetrates through the shell; the dosimeter card can be placed in the hollow cavity, and a drawer type drawing structure is formed between the dosimeter card and the shell; a plurality of sinking grooves are formed in the dosimeter card and are used for placing dosimeters; one end of the dosimeter card is provided with a pick-and-place card slot, the other end of the dosimeter card is provided with a first positioning card slot, and the shell is provided with a second positioning card slot corresponding to the first positioning card slot. According to the utility model, the volume of the dose box is reduced, the dose box is convenient to carry, and more dose boxes can be placed in the limited space of the thermoluminescence reader; a clamping structure is designed to prevent the card from falling out of the dosage box in daily wearing of the dosage box; the thermoluminescent dosimeter is easier to adapt to automatic equipment, and full-automatic reading of the thermoluminescent dosimeter is realized.

The invention discloses a crystal compound, a preparation method thereof and application of the crystal compound in X-ray detection, imaging and anti-counterfeiting encryption, and belongs to the technical field of crystals. The molecular formula of the crystal compound is [Cu (totp) (CH3CN) 3] [Cu2I3 (totp) (PN)]. (CH3CN), wherein totp is tris (o-tolyl) phosphine; and PN is diphenyl-2-pyridine phosphine. The crystal compound disclosed by the invention is simple in preparation method, and has the characteristics of large mass attenuation coefficient of X-ray energy, high light yield and low detection limit when being used as a material of an X-ray detector. The compound also has the characteristic of structural transformation in solvents such as methanol, ethanol, acetone, dichloromethane, tetrahydrofuran and the like, and meanwhile, the conversion of luminescence color under the excitation of 365nm ultraviolet light and X rays is accompanied. The material can be applied to the aspects of scintillator materials, room-temperature X-ray radiation indirect detection materials, radiation detection dosimeters, X-ray scintillator medical imaging, anti-counterfeiting encryption and the like.

The invention provides a scintillator film for a real-time X-ray dosimeter as well as a preparation method and application of the scintillator film. The preparation method comprises the following steps: weighing Eu (NO3) 3.6 H2O, Tb (NO3) 36H2O, Lu (NO3) 36H2O, NaF and NH4F to prepare powder B; preparing a rare earth fluoride material C from the powder B; weighing a polydimethylsiloxane prepolymer and a curing agent, adding the polydimethylsiloxane prepolymer and the curing agent into a cyclohexane solution, and performing ultrasonic dispersion to obtain a mixture D; adding the rare earth fluoride material C and PMMA particles into an ethanol solution, and uniformly dispersing to obtain a mixture E; dropwise adding the mixture E into the stirred mixture D, and performing vacuum mixing to obtain a mixture F; and transferring the mixture F to the surface of a ceramic plate which is respectively cleaned by water, ethanol and acetone and dried, coating to form a thin film, heating and annealing, and cooling to obtain the flexible scintillator thin film NaLuF4: Tb < 3 + > / Eu < 3 + > coated PDMS which is used for a real-time X-ray dosimeter.

The invention relates to a multi-sensor fusion radiology department environment safety monitoring method, device and equipment and a medium. The method comprises the following steps: performing dynamic calibration and alignment processing based on original heterogeneous data to obtain an aligned multi-source data stream, and obtaining the original heterogeneous data through a gamma dosimeter, a laser radar, a thermal infrared imager and an RFID positioning sensor; based on the aligned multi-source data flow, performing multi-modal data fusion and dose-environment mapping processing through an adaptive probability fusion network to obtain a three-dimensional dynamic dose field model and abnormal probability distribution; and according to the model and the abnormal probability distribution, risk matching and dynamic path planning processing are carried out in combination with a preset radiology department safety management rule, and an equipment control instruction and a robot navigation path instruction are obtained. According to the method, through multi-sensor fusion, dose field modeling and multi-dimensional risk decision making, the accuracy and real-time performance of radiology department environment monitoring can be improved, and comprehensive safety monitoring and intelligent decision making of the radiology department environment are achieved.

The utility model relates to the field of quality control of medical electron linear accelerators. Multi-dimensional radiotherapy dose measuring equipment comprises a multifunctional water tank, mounting grooves arranged in a matrix mode are formed in a bottom plate of the multifunctional water tank, the mounting grooves are used for placing thermoluminescence dosimeters, and film slots used for inserting films are formed in the bottom of the inner wall of the multifunctional water tank; three mounting holes with different heights are formed in a side plate of the multifunctional water tank, the mounting holes are used for being in butt joint with an ionization chamber plug or a water tank plug, and the water tank plug is used for blocking the mounting holes; the ionization chamber plug is used for installing the ionization chamber, and a through hole for inserting the ionization chamber is formed in the ionization chamber plug; the thermoluminescence dosimeter box further comprises a bearing bottom plate, bearing grooves distributed in a matrix mode are formed in the bearing bottom plate, and the bearing grooves are used for containing thermoluminescence dosimeters. By optimizing the structure of the water tank, compared with a traditional one-dimensional water tank, the dose measurement dimensionality is greatly improved.

The utility model relates to the technical field of medical dosimeters, and particularly discloses a personal dosimeter storage device which comprises a storage cabinet body, a plurality of storage drawers are arranged in the storage cabinet body, exhaust holes are formed in rear end plates of the storage drawers, a transverse partition plate is connected in the storage cabinet body, an air inlet cavity is formed in the transverse partition plate, and a plurality of air outlets are formed in the air inlet cavity. The lower end of the transverse partition plate is provided with an air inlet hole, and the rear end of the storage cabinet body is provided with an air inlet channel and an exhaust channel. By arranging the air box, dry air can be blown into the air inlet channel, then the dry air is blown to the storage drawer through the air inlet cavity and the air inlet hole, and finally the air is blown into the exhaust channel through the exhaust hole, so that the dosimeter stored in the storage drawer can be in a dry environment; the problems of corrosion, short circuit and the like of electronic elements or chemical substances in the dosimeter due to damp can be prevented, the normal working state of the dosimeter can be maintained, and the accuracy of a measurement result is ensured.

The application discloses a kind of gamma irradiation medium modules, including irradiation container and the several medium modules being arranged in irradiation container, irradiation container and medium module are cuboid structure;The length and height of single medium module are slightly less than the length and height of irradiation container one third respectively, the width of single medium module is slightly less than the width of irradiation container;The number of all medium modules=the number of medium module in full load in irradiation container * irradiation station number, irradiation station is used to place irradiation container;A dose field test and analysis method for gamma irradiation medium module is also disclosed.The application clearly medium module in irradiation container in loading mode and related parameters such as radiation safety, clearly irradiation device dose field is carried out mathematical simulation, the establishment of OQ dose field test coordinate system, dose meter is laid out mesh and point, the analysis use method of actual measurement dose data, provides proof data and technical basis, effectively improves core technical ability and quality assurance ability.

The utility model provides an eye crystal personal dosimeter which comprises a clamping ring used for clamping a head, the clamping ring is provided with two end portions, at least one end portion is connected with a rotating handle in a rotating mode, an installation groove is formed in the outer side of the free end of the rotating handle, the installation groove is detachably connected with a sealing cap, and the sealing cap is fixedly connected with the clamping ring. The thickness of the inner side of the end, connected with the clamping ring, of the rotating handle is reduced at the end, a rotating shaft is arranged on the inner side of the end, a limiting piece is arranged at the end of the rotating shaft, a flange protruding outwards is arranged at the end of the clamping ring, and a bayonet allowing the rotating shaft to enter and rotate is formed in the flange. The problems that in the prior art, wearing experience is poor, falling off is prone to occurring, sight is affected, wearing of the protection device is hindered, and wearing steps are tedious are solved.

The invention relates to a personal dosimeter for neutron and photon mixed radiation detection and a detection method, the dosimeter comprises a base, an upper cover and three groups of detection assemblies, and the base is provided with three grooves which are distributed in parallel and respectively accommodate a first detection assembly, a second detection assembly and a third detection assembly. The first detection assembly and the second detection assembly each comprise a neutron absorber with grooves formed in the upper portion and the lower portion and a 6Li thermoluminescence detector pair and a 7Li thermoluminescence detector pair, and separated measurement of the dose of thermal neutrons, medium-high energy neutrons and gamma rays is achieved. The third detection assembly comprises a neutron moderator and a solid track detector. Separation measurement of neutrons with different energies is realized through track density difference. The upper cover is provided with a measuring window, and tissue equivalent materials with different mass thicknesses are adopted and correspond to the dose depth of Hp (10) and the dose depth of Hp (3). Through combination of multi-channel reading and correction coefficient calculation, dose evaluation of gamma rays, thermal neutrons and fast neutrons on different tissue depths can be realized. The device is compact in structure, and is suitable for personal dose monitoring in a complex radiation environment.

The invention relates to the technical field of neutron measurement, and particularly discloses a thermoluminescence field dosimeter for measuring neutron energy spectrum.The thermoluminescence field dosimeter comprises a thermoluminescence field dosimeter body, and the thermoluminescence field dosimeter body comprises a front-end assembly, a rear-end assembly and a center assembly located between the front-end assembly and the rear-end assembly; the center assembly and the rear end assembly are detachably connected with the front end assembly. Wherein the distance between the front surface of the central assembly and the front surface of the front end assembly is 1mm, the distance between the front surface of the rear end assembly and the front surface of the front end assembly is 7mm, and the front surface of the central assembly and the front surface of the rear end assembly are respectively provided with a 6LiF thermoluminescence dosage piece and a 7LiF thermoluminescence dosage piece. The thermoluminescence field dosimeter is wide in neutron energy response range, covers 0.0253 eV-20 MeV, can be suitable for neutron energy spectrum measurement of nuclear facilities such as fission reactors, fusion reactors and medical accelerators, and is particularly suitable for measurement in measurement occasions with narrow spaces and large neutron field gradients.

This item is a personal dosimeter worn by workers in radiation handling facilities to detect radiation such as X-rays and gamma rays. The personal dosimeter consists of a main body and a clip. For example, when the main body is inserted into a breast pocket, the fabric of the breast pocket is sandwiched between the main body and the clip. A circuit board mounting a radiation detection unit and electronic circuits, etc. is provided within the main body. The radiation detection unit is located in an enlarged portion of the main body. A liquid crystal display that displays the dose rate, etc. is provided on the bottom of the main body.

The invention discloses a polytetrafluoroethylene free radical dosimeter for ionizing radiation dose measurement. The polytetrafluoroethylene free radical dosimeter is a spherical particle or a solid tablet prepared from polytetrafluoroethylene micro powder through the processes of mould pressing, sintering and the like. The polytetrafluoroethylene micro powder is polytetrafluoroethylene suspension resin generated through free radical polymerization of tetrafluoroethylene monomers, the tensile strength is larger than or equal to 30 MPa, the particle size is 200-300 microns, the melting point is larger than or equal to 322 DEG C, and the volume density is 550-590 g / L. The effective range of the polytetrafluoroethylene free radical dosimeter is 1-180 kGy, the free radical response of the dosimeter and the irradiation dose keep a direct proportion linear relation, the coefficient of determination R2 is equal to 0.999, and the polytetrafluoroethylene free radical dosimeter is especially suitable for ionizing radiation dose measurement of 100-180 kGy dose; and the total uncertainty of ionizing radiation ESR dose measurement is less than 5.02%.

The invention discloses a nuclear power radiation monitoring system and method.The nuclear power radiation monitoring system comprises an access control system, a radiation monitoring system, a cold dressing system, a channel monitoring system and a statistical prediction system.The access control system is arranged at an inlet and an outlet of a nuclear power plant, and the channel monitoring system is arranged in a channel of the nuclear power plant; the cold dressing system is arranged in the cold dressing room; the access control system is used for judging whether the personnel can enter or exit from the radiation control area according to the accumulated radiation value; the radiation monitoring system is used for collecting real-time radiation values and vital sign data of personnel; the cold dressing system is used for prompting dressing information and distributing dosimeters; the channel monitoring system is used for collecting radioactive contamination values and environmental radiation values of personnel in a channel; and the statistical prediction system is used for recording personnel identity information and predicting a future radiation value of the personnel.

The invention discloses a calorimeter and method for FLASH radiotherapy rays. The calorimeter comprises a calorimetric core, a jacket layer and a shielding layer. The calorimetric core is an absorber of FLASH radiotherapy rays, and the calorimetric core is nested in a first space in the jacket layer in a manner that a first interval exists between the calorimetric core and the jacket layer and the calorimetric core and the jacket layer are not in contact with each other; the jacket layer is nested in a second space in the shielding layer in a manner that the jacket layer and the shielding layer have a second interval and are not in contact with each other; no non-gas filler exists in the first interval and the second interval. Through the arrangement, the calorimeter aims to meet the strict requirements of ultrahigh dose rate and millisecond irradiation of FLASH radiotherapy rays, the defects that solid filler hinders heat transfer and increases heat capacity in the prior art are overcome, through the design that three layers do not make contact with each other and are free of solid filling, heat loss and heat conduction lag are reduced, heat is concentrated on the calorimetric core, and the heat loss is reduced. Meanwhile, the overall heat capacity is reduced, the millisecond-level thermal response speed is guaranteed, and high accuracy and traceability of dose measurement are guaranteed.

In general terms the aspects of the disclosed embodiments proposes a dose counter for registering a count of doses dispensed from an inhaler. The dose counter includes a counter ring including a circumferential drive feature. The dose counter also includes a worm comprising a shaft and a gear extending in a helical path about the axis of the shaft for driving the counter ring. The gear includes recesses uniformly distributed along the helical path. The dose counter further includes a cylindrical body including an engagement feature for driving the gear, the engagement feature extending in a helical or spiral path from the cylindrical body to engage the gear such that relative rotational movement between the cylindrical body and the worm rotates the worm about its shaft.

The utility model belongs to the technical field of radiation monitoring, and particularly relates to a placing rack for a radiation dosimeter in use, which comprises a support plate, a threaded table, a lifting table, a rotating seat, a sliding rod and the like, the threaded table is fixedly connected to the top end of the support plate, the lifting table is in threaded connection to the threaded table, the rotating seat is rotatably connected to the upper portion of the lifting table, and a placing groove is formed in the rotating seat. The multiple sliding rods are distributed with the center of the rotating base as the reference and slidably connected into the rotating base. Through the design of the rotating seat, rapid placement and positioning of the radiation dosimeter body are achieved, the stability of the radiation dosimeter body in the placement process is ensured by means of the synergistic effect of a sliding rod, a first spring and an arc-shaped clamping plate, and powerful support is provided for subsequent monitoring work; the problems of inconvenience and errors caused by the fact that the radiation dosimeter needs to be manually held by hand for monitoring for a long time are effectively solved.

The invention discloses an energy supply device and a dosimeter, and relates to the technical field of dosimeter design, the energy supply device can adopt an energy collector and a micro energy collection management circuit to complete collection and storage of micro energy of an indoor light source collected and converted by a solar panel or micro energy such as thermoelectricity and the like, and can supply energy to the dosimeter. The power supply device can supply power to some dosimeter equipment which is inconvenient to supply power and needs long-term unattended operation, and particularly can supply power to dosimeter equipment which cannot be conveniently supplemented by field monitoring and throwing type dosimeter equipment, so that long-term stable operation of the dosimeter equipment is guaranteed.

In the dosimeter material according to the present embodiment, a predetermined amount of nitrogen is added in the diamond.

A cabinet irradiator incorporates an x-ray tube, a moveable sample stage, dosimeter, and a real-time camera. A computing device receives video data from the real-time camera and based on the video data the computing device manipulates the sample stage height vertically in relationship to the sample chamber floor and the output window of the x-ray tube to be able to deliver the maximum dose rate to the entire sample as quickly as possible. A real-time image is captured and the image is correlated to move the sample stage vertically attaining a closer proximity to the exit window of the x-ray tube to attain and maximize dosage received by the sample in the shortest duration of time and operating the system to attain the desired prescribed dose.

The invention relates to the technical field of radiation dose measurement, and discloses a dosimeter laying caliper and a measurement method thereof.The dosimeter laying caliper comprises a base plate, a positioning groove, scale marks and a holding area, and the base plate is of a rectangular flat plate structure and provides a bearing face for dosimeter laying; the positioning grooves are uniformly distributed in the surface of the substrate, are designed according to a coordinate system of a dose field test, are rectangular grooves, are matched with fixed points of a dosimeter in size, and are used for limiting the placement position of the dosimeter; the scale marks are arranged along the middle part of the base plate, are made by adopting a laser etching or printing technology and provide auxiliary reference for a laying position; the holding area is located at one end of the base plate and is designed to be of a protruding or frame structure, and an operator can hold and move the caliper conveniently. According to the dosimeter laying caliper, the laying error is controlled within an extremely small range through the precisely designed positioning groove and the laser etched scale marks, and it is ensured that the dosimeter laying point completely meets the design requirement.

To provide a nondestructive inspection method and a nondestructive inspection device with which it is possible to measure the thickness reduction of a structure or the height of a deposit deposited inside the structure with better accuracy than conventional methods.SOLUTION: Provided is a nondestructive inspection method for measuring the thickness reduction of a structure or the height of a deposit deposited inside the structure by using a radiation transmission method. This inspection method includes: a transit dose measurement step (step S1) for scanning a sensor and measuring a transit dose (count Cn) having passed through the structure; and a height calculation step (step S4) for calculating a thickness reduction Δt of the structure or a height Δt of a deposit deposited inside the structure by using the transit dose (count Cn) at a measurement point and the transit dose (count C0) at a reference point given by a reference part estimation curve obtained by regressively analyzing the transit dose (count Cn) at the measurement point.SELECTED DRAWING: Figure 1

The invention relates to the technical field of radiation identification, and provides a personal dosimeter abnormal radiation identification method and system based on a time sequence LSTM, and the method comprises the steps: carrying out the abnormal value filtering, denoising and feature transformation processing of original dose rate data and environment parameter data collected by a personal dosimeter, and obtaining multi-dimensional time sequence feature data; inputting the multi-dimensional time sequence characteristic data into a long short-term memory neural network model for reasoning processing to obtain abnormal probability data reflecting the current radiation state; based on the abnormal probability data and the current environment background parameters, obtaining abnormal probability discrimination data through adaptive threshold dynamic adjustment; and performing multi-stage judgment processing on the abnormal probability judgment data to obtain an abnormal radiation identification result. According to the method, the false alarm rate caused by environment background fluctuation and the omission ratio of weak abnormal signals are reduced, and the progressive abnormity and the sudden abnormity are accurately recognized.

One embodiment of the present invention provides a method for producing a composition for a dosimeter, the method comprising a mixing step for mixing at least a portion of a plurality of raw materials for forming a composition for a dosimeter while supplying fine bubbles of an inert gas.

The application provides a wireless personal electronic dosimeter based on near field communication assisted positioning and a positioning method, and relates to the technical field of electronic dosimeters. A label deployment module acquires a basic layout for visualizing a staff position; a positioning trajectory generation module acquires a staff motion trajectory; a dose monitoring module collects real-time radiation dose data received by the staff; an information display module aligns the staff motion trajectory with the time sequence of the real-time radiation dose data and performs visual display; and a dose warning module is used for judging whether the radiation dose of the environment in which the staff is located exceeds a safe range, and if so, radiation warning is performed. The absolute position calibration of the near field communication physical label solves the floor misjudgment problem of traditional wireless positioning, improves positioning accuracy, realizes visual display of the staff position through label and map fusion display, and realizes fine management and control of radiation exposure through acquisition of position-dose dual information.

The invention discloses a multicolor rare earth scintillation crystal and a preparation method and application thereof, and belongs to the field of luminescent crystal materials and scintillation materials. The chemical formula of the multicolor rare earth scintillation crystal is [Ln (BDC) 1.5 (DMA)] n, wherein Ln is rare earth ion Tb < 3 + > and / or Eu < 3 + >, BDC is deprotonated terephthalic acid, and DMA is N, N-dimethylacetamide; n is infinity and represents continuous repeated infinite extension. The multicolor rare earth scintillation crystal has potential application value in multicolor fluorescent materials, X-ray detection and imaging materials and radiation detection dosimeters. The preparation method disclosed by the invention can be simply realized through solution reaction under relatively mild conditions, and is low in cost and high in industrial feasibility.

The utility model relates to a kind of card holder device of thermoluminescence dosimeter dose card, comprising: fixed shell, the inner cavity of fixed shell is inserted with the compatible carrier plate, recess is set in the top middle part of carrier plate, cover is connected in recess, receiving groove is set in the bottom two sides of recess inner cavity;Further comprising: limiting component, limiting component is set in the bottom of carrier plate, limiting component includes movable plate, spring is fixed in the top middle part of movable plate, the outer end of spring and the bottom of fixed shell are fixedly connected, the top two sides of movable plate are fixed with limiting post, limiting post is movably penetrated in fixed shell, the bottom of carrier plate is set with positioning hole corresponding limiting post, limiting post is inserted in positioning hole, the utility model is placed in receiving groove after dosimeter piece, and carrier plate is inserted into the inner cavity of fixed shell, and limiting component can be inserted in positioning hole to limit carrier plate, so as to be favorable to avoid the situation that dose card is easy to fall off after wear.