96 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 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 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.

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.

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 invention discloses a neutron-gamma dosimeter based on double detectors and a gamma and neutron dose rate detection method, the neutron-gamma dosimeter comprises a gamma detector, a neutron-gamma detector and a processing module, the gamma detector can only respond to gamma rays and output signals, and the neutron-gamma dosimeter can only respond to the gamma rays and output signals. The neutron-gamma detector can respond to neutrons and gamma rays and output signals, and the processing module can receive the signals of the gamma detector and the neutron-gamma detector, determine the gamma dose rate based on the output signals of the gamma detector, and determine the dose rate of the neutron-gamma detector based on the difference value of the output signals of the gamma detector and the neutron-gamma detector. And determining the neutron dose rate. According to the invention, through combination of the gamma detector and the neutron gamma detector, simultaneous monitoring and dose separation of neutrons and gamma rays are realized, doses of two radiation types can be accurately measured and distinguished, and use requirements in various complex environments are met.

The application provides a dose and focal spot measuring tool for an X-ray source, comprising: a base for placing an X-ray source; a supporting assembly comprising a connecting plate and an adjusting plate, the connecting plate being detachably connected with the base, and the adjusting plate being slidably connected with the connecting plate; a cavity comprising a bottom plate and a cavity sidewall, the bottom plate being fixedly installed on a side of the adjusting plate away from the connecting plate, and the bottom plate being provided with an X-ray source beam outlet clamping groove matched with a beam outlet direction of the X-ray source; and a mounting cylinder comprising a top plate and a mounting cylinder sidewall, a second beam outlet being arranged on a side of the top plate close to the cavity, and a slit test piece placing groove and a dosimeter placing groove being arranged on a side of the top plate away from the cavity, the relative positions of the cavity and the base in the vertical direction and the horizontal direction being realized, and the tool being capable of adapting to X-ray sources of various sizes.

The application provides a rare earth element doped radiation photoluminescence glass, a preparation method and application thereof, and solves the technical problem that the upper limit of a conventional radiation photoluminescence dosimeter is still insufficient for a high dose field. A glass component molar fraction expression of the rare earth element doped sodium aluminum phosphate silver glass is (1-x)[15.2%Al2O3-26.52%Na2O-58.06%P2O5-0.22%Ag2O]-xZ2O3, wherein Z is a rare earth element Lu or La, x is a molar fraction of Z2O3 in the rare earth element doped sodium aluminum phosphate silver glass, and 20%≤x≤40%. The rare earth oxide Lu2O3 or La2O3 is added into the sodium aluminum phosphate silver glass as a glass additive, the density of the glass is increased, more light emitting centers are formed, the glass has stronger ray blocking capacity, higher radiation detection efficiency, and better radiation dose-photoluminescence linearity, and the like; and the upper limit of a radiation dosimeter using the glass as a radiation photoluminescence material is improved.

The utility model discloses a radiation dosimeter, which belongs to the technical field of radiation detection and comprises a shell formed by assembling an upper shell and a lower shell. A circuit board is installed in the shell, and the two sides of the circuit board, the upper shell and the lower shell are arranged at intervals to form two electric device installation cavities; a toggle clip is arranged on the outer side of the shell. According to the utility model, the circuit board and the shell form two independent electric device mounting cavities, so that electric accessories in the device are arranged more compactly, and the size of the device is reduced; meanwhile, the toggle clip is arranged on the shell, so that the device is small in size and convenient to carry, an operator can give consideration to radiation measurement and other work, the working efficiency and quality are improved, and the time of being located in a radiation area is shortened.

The present application relates to a real-time monitoring method and system for radiation dose of a room where a staff member of a nuclear power plant works, comprising: after the staff member enters a control area of the nuclear power plant, a portable dosimeter acquires real-time radiation information of the staff member and real-time position information of the staff member; the portable dosimeter sends the real-time radiation information and the real-time position information to a background server; the background server receives the real-time radiation information and the real-time position information and triggers a calculation task; after triggering the calculation task, the background server calculates radiation data of the staff member in a current room according to the real-time radiation information and the real-time position information. The present application can refine the radiation condition of the staff member to a room level, provide more accurate and comprehensive dose information for radiation protection management, be more conducive to analyzing the radiation risk of the room, provide more powerful data support for formulating protection measures, and improve the safety of the staff member.

The utility model discloses a personal dose monitoring device based on intelligent wearing device, including dosimeter, the dosimeter bottom is equipped with adjustable quick -wearing mechanism, both sides of adjustable quick -wearing mechanism are equipped with connecting seat, be equipped with adjustable wearing mechanism on connecting seat, adjustable quick -wearing mechanism includes base and two embedded blocks, the base top is equipped with adjusting seat, the base inside is opened with movable slot, a plurality of limit posts are fixedly connected on the base inner wall, a plurality of movable round blocks are equipped on the limit post, belong to personal dose monitoring technical field. The personal dose monitoring device based on intelligent wearing device, through embedding the embedded block to the embedding seat, embedded block utilizes the slope and promotes the locking block to remove, and the locking block is locked to the inside of the card slot and is locked, and the convenient quick assembly and disassembly are carried out, and then the angle is adjusted to the adjusting seat, and the operation and use are convenient, thereby can effectively improve the convenience of use.

The application discloses a preparation method of a nitrate-based three-dimensional gel color change dosimeter, and comprises the following steps: dissolving a certain amount of nitrate in water to obtain a mixed solution I; adding a certain amount of a hydroxyl shielding agent to obtain a mixed solution II; adding a certain amount of a gel monomer, uniformly mixing, and heating to a certain temperature to obtain a mixed solution III; forming the gel monomer in the mixed solution III into a gel by a physical cross-linking method to obtain the gel dosimeter IV; adding a certain amount of a color developing agent to the surface of the gel dosimeter after the gel dosimeter is irradiated by high-energy rays for a certain dose, placing for 5 min to 20 min, removing the color developing agent on the surface of the gel, and thus the color change of gradually deepening color with the increase of the dose appears. The gel dosimeter can be used for detecting the treatment level of high-energy rays in clinical radiotherapy, the minimum detection limit is 0.1 Gy, the sensitivity is higher, the response speed is faster, and the gel dosimeter is more suitable for clinical radiotherapy dose detection.

This invention provides a method for measuring radiation dose that can be easily measured using readily available materials. [Solution] Using cellulose fibers or a structure made of cellulose fibers, radiation is irradiated onto the dosimeter material, thermogravimetric measurements are performed on the dosimeter material after radiation irradiation, the thermogravimetric rate of the dosimeter material is determined from the results of the thermogravimetric measurements, and the radiation dose corresponding to the thermogravimetric rate at any temperature within the range of 200°C to 300°C is obtained based on the correlation between the thermogravimetric rate and the radiation dose. As shown by arrows A and B in Figure 2, the electron beam irradiation energy (Dose) is estimated from the differential thermogravimetric first derivative rate (DTG).