146 results about "Dosimeter" patented technology

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.

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 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 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.

The X-ray imaging apparatus according to the embodiment includes an X-ray irradiator and processing circuitry. The X-ray irradiator is placed in a surgery room. The processing circuitry is configured to sequentially acquire a position of each staff member presenting in the surgery room during a procedure using the X-ray irradiator. The processing circuitry is configured to sequentially acquire an exposure dose of each staff member from a dosimeter. The processing circuitry is configured to associate the position of each staff member and the exposure dose of each staff member with a time, and sequentially record association data in a memory circuit. The processing circuitry is configured to display association data indicating a relation between the position of each staff member and the exposure dose of each staff member in an identifiable manner on a display.

The application discloses a kind of irradiation dose detection method, device, electronic equipment and readable storage medium, comprising: light source device emits initial light to detection pool, initial light passes through detection pool and dosimeter in detection pool, forms measurement light;Detector receives measurement light, and measurement light is distributed to each detection unit;Each detection unit detects the measurement light received by it, respectively obtains the unit absorbance of each detection unit;Unit absorbance reflects the absorbance of dosimeter under different index information;Data processor obtains dosimeter absorbance according to at least one unit absorbance;Data processor obtains irradiation dose result according to dosimeter absorbance of first measurement light and dosimeter absorbance of second measurement light.The application eliminates the occurrence of the light interference of different index information, improves the absorbance measurement precision, reduces the irradiation dose measurement error, and improves the data value.

The present invention relates to an integrated dosimeter comprising: a plurality of filters having different energy responses according to the type of incident radiation; a dose unit including a plurality of dose elements which are positioned to correspond to each filter and which generate light by radiation passing through each filter; and a plurality of optical amplification elements for converting the light generated from each dose element into current signals, wherein the plurality of filters include: a first filter, a second filter and a third filter having selective energy responses to beta rays, gamma rays and X-rays, respectively; and a fourth filter and a fifth filter having selective energy responses to neutrons, and also having selective energy responses to energy level of the neutrons.

The invention relates to a dosimeter (A) wearable by a human subject which includes:at least a first slow neutron sensor S1; a matrix containing a certain amount of absorbent material for slow neutrons;at least a second slow neutron sensor S2; a moderator consisting of or comprising polyethylene, hydrogenated plastic, water, paraffin or other hydrogenated or deuterated compounds.

The application provides a kind of intelligent distribution linkage cabinet control method and system for nuclear radiation control area, the method includes: receiving the operation request initiated by user on distribution equipment, by other means, complete user identity authentication and real-time check of nuclear power plant control area access authority;Judge its personnel type, and according to the first preset rule corresponding to personnel type, verify the validity of its radiation work permit and the matching of operation area and current control area entrance;Personal dosimeter is allocated and activated for user, and the unique identification of the dosimeter, user identity information and a specified locker establish logical binding relationship, when it is confirmed by hardware sensing that it has been taken away by user, send unlock instruction;When user initiates return operation and passes identity review, unlock the bound locker, and remove the binding relationship.The application can realize the systematic leap of nuclear radiation control area access management in safety, efficiency and intelligent level.

The application belongs to the technical field of high-energy ray shielding detection, and discloses a shielding container shielding performance detection device and method, the device comprises a shielding container, a thermoluminescence dosimeter, a detection source shielding sleeve, and a detection source, the detection source shielding sleeve is arranged outside the shielding container, the detection source is arranged inside the detection source shielding sleeve, the shielding container is provided with a plurality of detection points, and the inner surface of each detection point is pasted with a thermoluminescence dosimeter, and the method utilizes the device to detect the shielding performance. According to the application, a plurality of detection points are arranged inside the shielding container, a thermoluminescence dosimeter is arranged inside each detection point, gamma ray output is carried out by using the detection source on the outside, and then the reference value is obtained by using a shielding dose equivalent calculation formula, so that the shielding performance of the point can be detected.

The application provides a cleaning method for a current dosimeter baffle of an ion implanter, determines a previous ion source type in an ion implantation process and a to-be-converted ion source type; an electric field is applied, a processing gas is introduced into the ion implanter according to the previous ion source type, so that the first processing gas is ionized to form a first processing ion beam, the width of the first processing ion beam is a first mark size, and a first-stage cleaning treatment is performed on the current dosimeter baffle; according to the to-be-converted ion source type, a second processing gas is introduced into the ion implanter, so that the second processing gas is ionized to form a second processing ion beam, the width of the second processing ion beam is a second mark size greater than the first mark size, and a second-stage cleaning treatment is performed on the current dosimeter baffle. After the aging process pre-cleaning is performed on the current dosimeter baffle, the cleanliness of the current dosimeter baffle is obviously improved, and the overall off-line detection of the ion condition of the ion implanter can be obviously reduced.

1. The name of the design product: personal dosimeter. 2. The use of the design product: the design product is used for monitoring the personal cumulative dose and dose rate caused by X and γ radiation in the nuclear radiation environment. 3. The design points of the design product: in shape. 4. The picture or photo that best indicates the design points: front view.

Data storage device comprising an integrated circuit further comprising a control unit (100) and a storage array (400) of charge-based memory cells, wherein: the storage array (400) comprises a first subsection (410) that can be operated as a storage unit and a second subsection (420) that can be operated as a dosimeter; the control unit (100) is capable of providing a reference current (Iref) and To perform memory access operations in order to access memory with reference to the reference stream (Iref); and the control unit (100) is further capable of analyzing a statistical distribution of read streams (Iread) using memory access operations in the second subsection (420), the analysis comprising the following: counting logical reading errors of the Memory access operations and calibration of the reference current (Iref) depending on a number of counted logical read errors, which is also an indicator of total ionization dose (TID).

The invention belongs to the technical field of dosimeter calibration, and aims at solving the problems that a traditional dosimeter calibration method depends on manual operation, multi-test-point switching, data recording and off-line calculation need to be completed in a cesium source radiation field, efficiency is low, and test errors are likely to be introduced. According to the dosimeter intelligent calibration method and system based on the multi-modal algorithm, by designing a dual algorithm architecture of a measurement counting mode and an automatic scale mode, autonomous calculation of a gain correction factor and a background correction factor of a dosimeter is achieved, dose accumulation is monitored and stored in real time, and the accuracy of calibration is improved. Through a dynamic switching mechanism of external clock counting and port interruption counting, the stability of a radiation field is accurately judged, the sequential control precision of data acquisition is ensured, real-time calculation and storage of accumulated dose in a multi-gradient dose rate field are realized, and the continuity and traceability of calibration data are ensured. Through full-closed-loop automatic design, the problems of timing error, data input deviation and flow redundancy caused by manual operation are thoroughly eliminated.

Device (1) for detecting ionising radiation comprising: a first set (10) with a plurality of primary floating gate sensors (100) with a cumulative response proportional to a received ionising radiation; a second set (20) with a plurality of secondary floating gate sensors (200) with a cumulative response proportional to the received ionising radiation. The primary sensors (100) have a sensitivity to ionising radiation above a first threshold. The secondary sensors (100) have a sensitivity to ionising radiation above a second threshold lower than the first threshold, whereby the first set (10) is configured to detect ionising radiation in a first range and the second set (20) is configured to detect ionising radiation in a second range, and the first range is lower than the second range.

The application relates to the technical field of neutron personal dose, and provides a neutron personal dosimeter, which comprises a first detection module, a second detection module, a back-to-back detection module and a third detection module, the first detection module is used for measuring full-energy-region neutrons; the second detection module is used for measuring fast neutrons; the back-to-back detection module is used for discriminating spatial high-energy charged particles; and the third detection module is used for measuring full-energy-region neutrons, and the sensitivity of the third detection module to medium-energy neutrons is higher than that of the first detection module; a first slow-down wrapping part wraps at least part of the first detection module; a second slow-down wrapping part wraps at least part of the second detection module; a first absorption wrapping part wraps at least part of the back-to-back detection module; and a second absorption wrapping part wraps at least part of the third detection module, so that the neutron personal dosimeter is suitable for measuring the neutron personal dose equivalent in a cosmic space environment.