90results about "Luminescent dosimeters" patented technology

The invention relates to the technical field of nuclear radiation detection management, and discloses a nuclear radiation detection management system based on artificial intelligence, comprising: a dynamic sensing module which detects nuclear radiation through quantum sensing to obtain radiation data, captures NV color center fluorescence intensity, analyzes to obtain gamma ray dose rate, constructs a nanoscale olfactory receptor simulation structure, and sends the radiation data to a control module; radioactive gas is detected and cooperatively monitored; the reasoning calculation module is used for analyzing space-time correlation based on radiation data, optimizing algorithm to accelerate result output, adjusting calculation complexity by calculating dynamic weight distillation, and correcting data transmission in real time; the decision management module is used for constructing a four-dimensional causal graph based on the radiation data, performing intervention simulation, evaluating a decision long-term effect, screening an optimal decision, and performing adversarial training based on historical repair case data; and the fusion cooperation module is used for establishing a cross-mechanism federated learning framework, carrying out hash operation on the radiation data, and establishing an NFT (Network Fourier Transform) on a block chain through an intelligent contract for query, verification and transaction.

The invention discloses a portable thermoluminescence dosage device based on photon counting, and relates to the technical field of nuclear radiation detection equipment, the portable thermoluminescence dosage device comprises a shell, a rack, a heating module, a photon counting module and a movement module, and accurate measurement is realized through cooperation of multiple modules. In the motion module, a cam shaft, a rotating handle and a rolling bearing are matched to drive a heating cavity to drive a heating plate to move flexibly, and a guide hole of a heating supporting table guarantees moving stability. The dosage piece positioning plate accurately positions the dosage piece, the heating plate stably heats, and the reset spring buffers and assists the heating cavity in resetting, so that the device is ensured to run circularly. The filter group is accurately mounted and is matched with the sealing ring to isolate external interference, so that the detection accuracy of the photon sensor is improved, and the measurement precision is guaranteed. The device shell is provided with the display screen and the charging interface, data can be displayed in real time, charging is convenient, portability and practicability are enhanced, and the device is suitable for portable thermoluminescence dosage measurement in multiple scenes.

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.

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

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.

A high-sensitivity optical fiber irradiation monitoring device and method, comprising: first measuring the i The initial mode instability threshold P of the fiber laser oscillator in a non-irradiated environment before the first operation 1,i According to the i The irradiation environment corresponding to the first work is set according to the response requirements of the total irradiation dose. i The working power P of the fiber laser oscillator under the irradiation environment corresponding to the second work 2,i , P 2,i <P 1,i , working power P 2,i and the initial mode instability threshold P 1,i The closer the fiber laser oscillator is, the more sensitive it is to the total irradiation dose. i The present invention operates under the irradiation environment corresponding to the second operation, and monitors in real time whether the fiber laser oscillator has reached the mode instability threshold under the current irradiation environment. By monitoring whether the fiber oscillator has mode instability, the present invention can determine whether the fiber laser oscillator has reached a certain total irradiation dose under the current irradiation environment, with a highly sensitive monitoring effect.

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 present invention relates to the field of radiation dose measurement technology, and provides a thermoluminescent dose device whose energy response is positively correlated with the energy of rays. By arranging an energy compensation filter in front of a thermoluminescent sheet, the problem that most thermoluminescent dosimeters have too high instrument response in the energy range of 20-100keV is solved, and the energy response curve of the thermoluminescent dosimeter is improved, so that the energy response of the thermoluminescent dosimeter is in a monotonically increasing relationship with the incident X / γ-ray energy, thereby improving the measurement accuracy of the thermoluminescent dosimeter. By opening a hole in the energy compensation filter and arranging an anti-scattering sheet behind the thermoluminescent sheet, the energy response of the thermoluminescent dosimeter in the low energy region is improved, and the technical effect of the detection lower limit of the thermoluminescent dosimeter in the low energy region is maintained.

The present invention uses the concept that radiation-sensitive material (4) embedded in a disposable radiochemistry device gives the device the additional capability of recording radiation dose, for readout at a later time. The invention provides a device comprising at least one piece of a radiation-sensitive material (4), and a method to measure the radiation dose associated with radiolabelled compound produced by said device.

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 utility model relates to an irradiation field scattered radiation measuring device for boron neutron capture therapy equipment, which comprises a horizontal support rod provided with scales; the adjustable supports are arranged at intervals and used for supporting the horizontal supporting rods and adjusting the heights of the horizontal supporting rods; and the multiple groups of measuring assemblies are detachably clamped on the horizontal supporting rod, and the positions of the measuring assemblies clamped on the horizontal supporting rod can be adjusted according to measurement requirements so as to measure the field scattered radiation dose of the boron neutron capture therapy equipment. According to the scheme of the utility model, the horizontal supporting rod and the measuring assemblies clamped on the horizontal supporting rod can be adjusted to a proper height through the plurality of adjustable brackets, and then each group of measuring assemblies can be accurately adjusted to related positions according to the scales on the horizontal supporting rod according to measurement requirements so as to accurately measure the scattered radiation dose. The leakage radiation level of the boron neutron capture therapy equipment is scientifically controlled, normal tissues are prevented from receiving unnecessary excessive radiation, and the safety of patients is protected.

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.

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

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.