64results about "Luminescent dosimeters" patented technology

The invention discloses a radiation dose detection method and system for an irradiation cross-linked area, and belongs to the technical field of radiation dose detection.The method specifically comprises the steps that coordinates of a to-be-detected core point and coordinates of related points around the to-be-detected core point are input, and transient fluorescence spectrums, thermoluminescence signals and conductivity change data of all the points in an irradiation window are synchronously collected; constructing a physical configuration association model based on association point distribution, and forming a scattered field association data network; when the residual error between the actually measured data of the core point and the model predicted value exceeds a dynamic threshold value, activating the reverse solving process of the scattered field, reversely reconstructing a theoretical data sequence of the core point by using associated node data, and replacing interfered original data; and finally, inputting the reconstructed sequence into a dose calculation model, and outputting a corrected radiation dose value. According to the invention, measurement errors caused by local material non-uniformity and instantaneous interference can be effectively reduced, and the reliability of dose detection is improved.

A method and system for determining a radiation dose is provided. The method can include receiving at least one polarized signal from a radio-luminescent element and determining a degree of linear polarization and an angle of linear polarization of the at least one polarized signal based on at least one predetermined polarization transmission axis. The system can include a polarization sensitive sensor for capturing at least one polarized signal from a radio-luminescent element; and a processor. The processor can be configured to: receive the at least one polarized signal; and determine a degree of linear polarization and an angle of linear polarization of the at least one polarized signal based on at least one predetermined polarization transmission axis.

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 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 application provides a radiation total dose detection system and method based on a radiation color-changing film, and the system comprises a luminosity detection system, a chroma detection system and a calculation module; the luminosity detection system is used for detecting the change of light power transmitted by the first radiation color-changing film; the chroma detection system is used for acquiring the image of the second radiation color-changing film; and the calculation module is used for determining the radiation total dose according to the change of light power and / or the image. The application is based on the corresponding relationship between the transmittance of the radiation color-changing film and the received radiation total dose, that is, when the light power loss transmitted by the film increases, the transmittance of the film decreases, and the received radiation total dose increases; when the color of the film image deepens, the transmittance of the film decreases, and the radiation total dose increases. Thus, the real-time monitoring of the radiation dose is carried out from two angles of the change of transmitted light power and the change of image color, respectively, and the online detection of the radiation total dose of the target environment is realized.

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 utility model relates to the technical field of measuring instrument storage, in particular to a portable thermoluminescence dosage measuring instrument. The measuring instrument comprises an outer box and a measuring instrument body, a sliding drawing mechanism is arranged outside the outer box, the sliding drawing mechanism comprises a sliding cover arranged on one side of the outer box in a sliding mode, and the sliding cover and the measuring instrument body are fixedly arranged. According to the device, rapid taking and placing of the measuring instrument body are achieved through the sliding drawing mechanism, the sliding cover and the measuring instrument body are fixedly connected through the first fixing bolt, and by means of sliding fit of a sliding block and a sliding groove and detachable connection of a buckle, the measuring instrument body can be rapidly taken and placed. A user only needs to open the buckle and pull the sliding cover to pull the whole measuring instrument body out of the outer box, the tedious step that a traditional instrument needs to be separated from an anti-seismic structure is omitted, the operation process is greatly simplified, meanwhile, the sliding drawing mechanism has the limiting function, the relative stability of the measuring instrument body and the outer box in the carrying process is ensured, and the measuring instrument is convenient to carry. And the shaking risk is avoided.

A sensor and a sensing device for determining a radiation dose, a readout device for reading out a sensor, and a method for determining a radiation dose, the sensor (110) comprising: an organic material, the organic material having a radiation dose-dependent light emission characteristic such that a characteristic light emission is generated from the organic material once the organic material has accumulated a radiation dose greater than a threshold radiation dose characteristic (172), the sensor (110) being further configured such that a difference of the threshold radiation dose characteristic (172) and a radiation dose accumulated in the material represents a to-be-determined radiation dose.

The application relates to a ratio type radiation sensing device with nonlinear response to dose rate and a use method thereof, and relates to a scintillator radiation measuring device with nonlinear change of luminous intensity and use method, and aims to solve the technical problems of low measuring precision, complex structure, poor reliability, poor real-time performance and poor applicability of existing radiation sensors. The ratio type radiation sensing device with nonlinear response to dose rate comprises an X-ray excitation module, a mixed sensing probe and a light signal collection module; wherein the mixed sensing probe is a round piece pressed by uniformly mixing NaLuF4:3Pr,5Er nanocrystals and NaLuF4:3Ce nanocrystals. The use method of the device is a standard curve method. The device can realize accurate detection in a wide range of 1.86-14.95 mGy / s, and can be used in the fields of environmental monitoring, biomedical imaging and public security inspection.

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 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 crystalline lens radiation dose measuring device and glasses, and the crystalline lens radiation dose measuring device comprises a body which is provided with a cavity for accommodating a radiation detector; the body is further provided with a window, and the radiation detector enters the cavity through the window. The window closing unit comprises a plug, and the plug is matched with the window; when the plug is arranged on the window, the cavity is a closed cavity; clamping grooves are further formed in the two sides of the body; the end parts of the glasses leg clamping parts are matched with the clamping grooves; the glasses leg clamping part is of a C-shaped structure; and the glasses leg clamping parts are movably arranged on the back surface of the body.

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 invention relates to a porous material which comprises a metal-organic framework material, and the metal-organic framework material comprises metal ions and an organic ligand; wherein the metal ions are copper ions (Cu < 2 + >) and cerium ions (Ce < 3 + >), and the organic ligand is selected from pyridine groups; at least 80% of micropores of the porous material have pore diameters. In addition, the invention also relates to the synthesis of the porous material and the use thereof. The porous material researched, developed and synthesized by the invention breaks through the difficult problem of rapid and high-sensitivity measurement of the activity concentration of Kr-85 in the gaseous effluent of the nuclear facility, so as to realize effective monitoring of the discharge amount and the abnormal operation state of the nuclear facility, support the safe and stable operation of the nuclear facility, and guarantee the safety of personnel and environment.

The utility model discloses a static three-dimensional water tank for BNCT midpoint dose measurement, which comprises a three-dimensional water tank, a static measurement device is arranged on the three-dimensional water tank, and a plurality of thermoluminescent sheet detectors for measuring multi-point dose in the three-dimensional water tank are arranged on the static measurement device. According to the static three-dimensional water tank for BNCT midpoint dose measurement, TLD is conveniently taken and placed through the static measurement device, accurate measurement of particles is completed, metering of multiple points in the water tank can be simultaneously measured in cooperation with a TLD detector, time can be saved, particle irradiation time can be shortened, and measurement of multiple positions can be completed at a time; the problem that a dynamic water tank is not suitable for multi-point measurement is solved. The problem that a dynamic three-dimensional water tank is not applicable is solved; the dosage of multiple point locations in the three-dimensional water tank can be measured at the same time in cooperation with TLD, and compared with single-point-location measurement of a dynamic three-dimensional water tank, the particle irradiation time can be shortened, and the detection efficiency can be improved.

The application discloses a preparation method and application of a halogenated 2,1,3-benzothiadi-azolyl blue light molecule, and the method comprises the following steps: taking 2,1,3-benzothiadi-azolyl as a parent body, and coupling corresponding boric acid and a halogenated acceptor in a mixed solvent of tetrahydrofuran and water under the action of a palladium catalyst to obtain a target product after purification. The molecule shows obvious hybridization and charge transfer properties, realizes high triplet exciton utilization rate through a high-energy state reverse intersystem crossing process, effectively enhances spin-orbital coupling by introducing heavy atoms, and improves the absorption capacity to high-energy radiation, so that the molecule has the outstanding advantages of super-short fluorescent lifetime and high photoluminescence efficiency, and provides a new solution for developing a new generation of organic luminescent materials with super-short lifetime, high efficiency and low cost.

The thermoluminescent dosimeter comprises a shell and an inner core, the inner core comprises a plurality of thermoluminescence elements, and the first thermoluminescence element and the second thermoluminescence element are arranged in the shell; a first upper window is arranged on the upper surface of the shell corresponding to the area of the first thermoluminescence element, and a second upper window is arranged on the upper surface of the shell corresponding to the area of the second thermoluminescence element; a first lower window is arranged on the lower surface of the shell in a region corresponding to the first thermoluminescence element, and a second lower window is arranged in a region corresponding to the second thermoluminescence element; a first upper filter disc is arranged on the first upper window, a first lower filter disc is arranged on the first lower window, a second upper filter disc is arranged on the second upper window, and a second lower filter disc is arranged on the second lower window; the first upper filter disc and the first lower filter disc are made of the same material; the second upper filter disc and the second lower filter disc are made of the same material; the material of the first upper filter disc is different from that of the second upper filter disc; and the first upper filter disc comprises high-molecular plastic or solid metal.

The present invention relates to a phantom for dosimetry comprising a composition comprising nanoparticle crystallites characterised by exhibiting optically stimulated luminescence properties, and wherein said crystallites are embedded in a hydrogel matrix. Furthermore the present invention relates to a dosimeter based on said phantom for measuring ionising radiation, and more particularly to a phantom for three-dimensional dosimetry via optically stimulated luminescence and corresponding method for preparation and use.

A ring for monitoring the radiation dose of a finger part comprises a dosimeter body which is in the shape of a thin film dose bag; the dosage piece is sealed in the dosimeter body; a window is arranged on the dosimeter body, and a skin simulation unit is arranged on the window; the dosimeter body is made of any one or a combination of at least two of an aluminized polyester film, polypropylene, polyethylene or polyvinyl chloride and is of a laminated structure; when the dosimeter body comprises a combination of at least two of an aluminized polyester film, polypropylene, polyethylene or polyvinyl chloride and is in a laminated structure, each layer is composed of any one of the aluminized polyester film, the polypropylene, the polyethylene or the polyvinyl chloride. The dosimeter body is simple in structure, monitoring data of the fingers of a worker are obtained, and meanwhile the worker feels more comfortable when wearing the dosimeter body for a long time.

The invention relates to a porous material which comprises a metal-organic framework material, and the metal-organic framework material comprises metal ions and an organic ligand; wherein the metal ions are aluminum ions (Al < 3 + >) and cerium ions (Ce < 3 + >), and the organic ligand is selected from 1, 2, 4, 5-tetra (4-carboxyl phenyl) benzene; at least 80% of micropores of the porous material have pore diameters. In addition, the invention also relates to the synthesis of the porous material and the use thereof. The porous material researched, developed and synthesized by the invention breaks through the difficult problem of rapid and high-sensitivity measurement of the activity concentration of Xe-133 in the gaseous effluent of the nuclear facility, so that effective monitoring of the discharge amount and the abnormal operation state of the nuclear facility is realized, safe and stable operation of the nuclear facility is supported, and the safety of personnel and environment is guaranteed.

The invention relates to the technical field of radiation monitoring, in particular to a ring type radiation detector. The ring-type radiation detection meter comprises a device shell and ring belts installed at the two ends of the device shell. Any one of the two sides of the device shell is provided with a mounting slot extending into the device shell, a detection inner core is inserted into the mounting slot, and a radiation detection element is sealed on the detection inner core through a transparent sealing sleeve; a first through hole extending to the mounting slot is formed in the position, corresponding to the radiation detection element, of the device shell, an annular table top is arranged in the first through hole, a filter membrane is arranged on the annular table top, and a closed space is formed between the filter membrane and the detection inner core; and a metal pressing ring welded with the device shell is also arranged on the filtering membrane. According to the ring-type radiation detector, leakage of the radiation detection element is avoided, the service life of the radiation detection element is prolonged, and the measurement accuracy of the radiation detection element is improved.

A crystalline lens radiation dose measuring device comprises a body in the shape of a thin film dose bag; a dosage piece and an energy compensation piece are wrapped in the body in a sealed mode. The body is made of any one or a combination of at least two of an aluminized polyester film, polypropylene, polyethylene or polyvinyl chloride and is of a laminated structure; when the body comprises a combination of at least two of an aluminized polyester film, polypropylene, polyethylene or polyvinyl chloride and is in a laminated structure, each layer is composed of any one of the aluminized polyester film, polypropylene, polyethylene or polyvinyl chloride. The dosage piece is sealed in the body, so that the dosage piece is isolated from the outside, and the phenomena that the dosage piece is affected with damp and polluted are avoided.

The utility model relates to the fixed field of dose card, concretely relates to a kind of fixing device of thermoluminescence dosimeter dose card.It includes fixed shell, the inside sliding connection of fixed shell has dose card body.The utility model is through the mechanical clamping of moving rod and card block, cooperate the elastic limit of spring piece and the elastic limit of dose card body clamping groove, form double fixed structure, when dose card body is pushed into fixed shell, moving rod is slid along moving trajectory groove to the card block gap groove and completes clamping, can bear external force and not loose when pulling;At the same time, spring piece is embedded in the clamping groove of dose card body, limit its vertical direction displacement, ensure that dose card still keep stable when being vibrated, collided or personnel movement, will not occur displacement or overturn, effectively avoid the radiation measurement error caused by position change, guarantee the accuracy of measurement data;And, only dose card body is pressed inwards again, unlocking mechanism can be triggered, pressing action promotes moving rod from card block gap groove and separates.

The utility model relates to the field of radiation monitoring devices, and particularly provides an energy identification type radiation dose monitoring device. The thermoluminescence dosimeter comprises an observation assembly and a monitoring assembly, the observation assembly comprises an observation box, glass plates are arranged at the front end and the rear end of the observation box, a lifting opening is formed in the top end of the observation box, the monitoring assembly comprises a sealing plate, and four sets of thermoluminescence dosimeter bodies are arranged at the bottom end of the sealing plate. Through cooperation of the observation assembly and the monitoring assembly, the problems that an existing thermoluminescence dosimeter can only monitor and record the radiation dose of single energy, dosimeters with phosphors of different atomic numbers need to be replaced if different energy needs to be monitored, the radiation doses of different energy cannot be identified and monitored at the same time, and the energy consumption is low are solved. And the whole structure is simple and stable, use is convenient and fast, and good practicability is achieved.

This invention provides a method and system for re-screening thermoluminescent detector dispersion. It utilizes medical and industrial radiation source equipment to provide the radiation field for thermoluminescent detector dispersion screening, and optimizes the irradiation geometry of the thermoluminescent detectors, eliminating the dependence on dedicated radiation sources in the dispersion screening process. This significantly lowers the hardware threshold, simplifies the re-screening operation, and improves the overall quality and efficiency of thermoluminescent dose monitoring. By processing the thermoluminescent detector readings, this invention first eliminates thermoluminescent detectors with outlier measurement results, then recalculates the average value of the sampled specimens after outlier removal, calculates the dispersion control range for this batch of thermoluminescent detectors, and finally eliminates thermoluminescent detectors with outlier measurement results again, ensuring the accuracy and reliability of the re-screening results.

A biodegradable wireless dosimetry system (100) for in vivo verification of radiotherapy, wherein the system (100) comprises: a biodegradable wireless in vivo dosimeter unit (1); and an external reading unit (2) wirelessly coupled to the biodegradable wireless in vivo dosimeter unit (1); the biodegradable wireless in vivo dosimeter unit (1) comprises: a power receiving and rectifying unit (PWR) comprising a near-field receiver (3) and a rectifier (4) implemented with at least one biodegradable conductor or biodegradable compound (5), wherein the power receiving and rectifying unit (PWR) is configured to receive electromagnetic energy from the external reading unit (2) and generate a DC power supply; an energy buffer block (ENB) comprising a biodegradable electrochemical energy buffer (6) configured as a Zn-ion hybrid micro-supercapacitor (7), electrically coupled to the rectifier (4) and designed to stabilize the DC power supply during intermittent wireless coupling; a radiation sensor block (RSB) with a radiation transduction module (8) configured to generate a dose-proportional signal in response to absorbed ionizing radiation; an optional physiological sensor block (PSB) with at least one additional physiological sensor (20); a telemetry and control block (TCB) (40) configured to process the dose-proportional signal and all physiological sensor signals and to provide wireless telemetry to the external reading unit (2); and a resorbable encapsulation block (9) enclosing the near-field receiver (3), rectifier (4), energy buffer (6, 7), radiation transduction module (8), physiological auxiliary sensor (20) and telemetry and control block (40), wherein the resorbable encapsulation block (9) is configured to maintain the integrity of the device during a predefined clinical monitoring period and is subsequently biodegraded under physiological conditions; wherein the external reading unit (2) comprises a corresponding block diagram architecture: a coupling and power transfer block (CPB) with a transmit / receive coil (35) configured to couple with the near-field receiver (3) and to power the biodegradable wireless in vivo dosimeter unit (1); a signal processing block (SPB) (36) configured to demodulate and process telemetry data received from the telemetry and control block (40); a memory block (38) configured to store calibration data and measured dose information; and a user interface block (37) configured to display at least one parameter indicating the absorbed dose for verification of a radiotherapy plan, wherein the blocks (PWR, ENB, RSB, PSB, TCB, CPB, SPB, memory block (38) and user interface block (37)) are arranged such that a block diagram of the system (100) is defined by these functional units and their interconnections.

The invention relates to the technical field of radiation monitoring, in particular to a watch with a radiation detection function. The watch comprises a watch shell, and a radiation detection assembly is inserted into the watch shell. The radiation detection assembly comprises a device shell, any one of the two sides of the device shell is provided with an installation slot extending into the device shell, a detection inner core is inserted into the installation slot, and a radiation detection element is sealed on the detection inner core through a transparent sealing sleeve. A first through hole extending to the mounting slot is formed in the position, corresponding to the radiation detection element, of the device shell, an annular table top is arranged in the first through hole, a filter membrane is arranged on the annular table top, a closed space is formed between the filter membrane and the detection inner core, and a metal pressing ring welded to the device shell is further arranged on the filter membrane. According to the watch with the radiation detection function, leakage of the radiation detection element is avoided, the service life of the radiation detection element is prolonged, and the measurement accuracy of the radiation detection element is improved.

The present invention relates to a method for analyzing a radiation dose to which a thermoluminescent dosimeter element is exposed, and to an analysis device therefor. The analysis method according to the present invention comprises the steps of: heating an exposed thermoluminescent dosimeter element and measuring light emitted for each channel according to temperature; converting the measured light into charge amounts to obtain a glow curve; and removing spikes corresponding to outliers from the glow curve, wherein the removing the spikes includes: for charge amounts of m consecutive channels, if a difference in charge amounts between the last two channels exceeds a threshold value, correcting the charge amount of the last channel by extrapolating charge amount of the preceding three channels, where m is an integer from 4 to 10.

The invention discloses single Eu-doped perovskite fluorescent powder and a preparation method and application thereof, and belongs to the technical field of luminescent materials, the molecular formula is NaYSrWO6: xEu < 3 + >, and x is equal to 0.005-0.5. The preparation method comprises the following steps: weighing the raw materials according to the stoichiometric ratio, mixing and grinding, heating and preheating the obtained powder, quickly heating and calcining, and crushing and grinding after calcining to obtain the Eu-singly-doped perovskite fluorescent powder. The double-perovskite tungstate NaYSrWO6: xEu < 3 + > fluorescent powder provided by the invention can have both high-efficiency photoluminescence (PL) and thermoluminescence (TL) performances, and has application potential in the aspects of white light LED, real-time low-dose-rate accurate measurement and X-ray imaging.