62 results about "External irradiation" patented technology

The invention discloses a spatial projection regularization method for sound source localization and sound field reconstruction and a related device, and belongs to the technical field of sound source localization. Specifically, according to the method, an equivalent source method model is utilized, and an external radiation sound field of a sound source to be measured is simulated through a series of virtual sources. Then, according to the first sound pressure transfer matrix from the virtual source arrangement surface to the holographic measuring point plane and the sound pressure of the holographic measuring point, a space projection regularization algorithm is used for solving the inverse problem, and therefore the equivalent source intensity is obtained; and then, reconstructing an external radiation sound field of the sound source to be detected by using the second sound pressure transfer matrix and the equivalent source intensity. And finally, by taking the maximum sound pressure amplitude as a standard, screening field points in an external radiation sound field so as to determine the position of the sound source to be detected. According to the space projection regularization algorithm, truncation processing of the vector space is carried out with the projection size of the measurement information in the vector space as the criterion, real information is reserved, and noise interference is restrained to the maximum extent.

The invention relates to an alpha radiation detector (1) for measuring the radon concentration in the ambient air, comprising a housing (10) having a base (5) on which a hood (2) is arranged, which hood has a chamber (9) which is located therein, wherein the opaque housing (10) is designed in such a way that ambient air can penetrate into the chamber (9) from the outside, the alpha radiation detector further comprising an optical sensor (4). According to the invention, the hood (2) has an inner wall which is provided at least in part with a scintillation material (3) which generates light pulses (8) upon impingement of alpha particles (7), which light pulses are sensed by the optical sensor (4).

The invention relates to a method for evaluating the radiation dose of special public nearby a nuclear facility, and the method comprises the steps: estimating the concentration distribution of radionuclides in air, surface soil and a biological medium nearby the nuclear facility through collecting the radiation dose evaluation parameters of a target special public and combining an environment quality evaluation model; based on the data, the annual effective dose of the target special public at the nuclear facility boundary and the living quarter is calculated, and a plurality of ways such as inhalation internal irradiation, air immersion external irradiation, surface deposition external irradiation and ingestion internal irradiation are considered. In addition, a dynamic calculation method is also introduced, especially for the influence of year-by-year change of the cumulant of radionuclides deposited on the earth surface, factors such as decay, resuspension and infiltration into underground water of nuclides are fully considered, and the accuracy and foresight of evaluation are improved. Accurate and comprehensive technical support is provided for radiation protection of the special public around the nuclear facility, and the requirements of the nuclear facility public for dose monitoring and risk management are met.

The invention discloses a gradient thermocouple liquid level real-time detector, and relates to the technical field of liquid level detection, an integrated gradient thermocouple probe rod structure is adopted, a plurality of groups of thermocouple nodes are integrated on a single corrosion-resistant alloy integrated gradient thermocouple probe rod according to a preset interval through a special process, and a continuous temperature gradient sensitive area is formed. A high-precision signal processing circuit is embedded in the integrated gradient thermocouple probe rod, the temperature difference potential of each node is collected in real time, the liquid level height is calculated based on a dynamic temperature field modeling algorithm, and full-scale continuous measurement is achieved. Gradient node distributed layout is created for the first time, and a blind area of traditional point type measurement is eliminated; a self-adaptive temperature compensation mechanism is developed, and medium layering and boiling interference are overcome; the integrated gradient thermocouple probe rod adopts vacuum sealing and a nanometer heat insulation coating, and can resist a high temperature of 600 DEG C and a high pressure environment of 40 MPa. The device has millimeter-level measurement precision and millisecond-level dynamic response capability, does not need to move parts or external radiation sources, and remarkably improves the reliability, safety and installation convenience of liquid level monitoring of industrial reaction kettles and high-pressure boilers under extreme working conditions.

The invention provides a radioactive biological experimental facility radiation environment monitoring and personal dose monitoring method, which comprises a fixed radiation dose monitor, a portable radiation dose monitor, a personal dose instrument, an experimental facility computer system docking port, an analysis center and an early warning judgment module, the experimental facility environment radiation dose can be monitored in real time, single-time operation personal cumulative doses under three different conditions can be obtained through an experimental facility computer system, radiation dose summary analysis can be carried out on radioactive sources operated in the experimental facility, radiation dose changes under different radioactive source operations are obtained, and the experimental facility environment radiation dose monitoring system can be used for monitoring the experimental facility environment radiation dose in real time. And finally, performing early warning according to the environmental radiation dose and the individual accumulated dose result. The environment radiation state can be monitored timely, accurately and effectively, and the external irradiation dose of personnel can be monitored and evaluated in real time.

The invention discloses a nuclear accident external irradiation dose field calculation method based on a limited smoke cloud model and a computer readable storage medium, and solves the technical problems of poor matching performance, relatively long calculation time, relatively low efficiency and the like in the prior art. The method comprises the following steps: firstly, acquiring a radionuclide source item file released by a nuclear accident and corresponding original data; calculating to obtain a source item nuclide information data matrix; according to the gamma ray energy of each nuclide, calculating to obtain a gamma ray linear attenuation coefficient and an air energy mass absorption coefficient of each nuclide; calculating to obtain the grid number and the grid number of each grid penetrated by gamma rays of other grids in the smoke cloud activity concentration field and the ground deposition activity field; finally, the deposition external irradiation dose and the smoke cloud external irradiation dose of each grid are obtained through calculation, and therefore nuclear accident external irradiation dose field calculation is completed. According to the method, automatic and refined calculation of the external irradiation dose during the nuclear accident can be realized, and the calculation efficiency is relatively high.

The invention discloses a passive radar target positioning method and system based on an external radiation source, and relates to the technical field of radar positioning, and the method comprises the steps: screening an external radiation source signal set of a target monitoring region, laying a distributed receiving antenna array based on the signal set, receiving a signal in real time, and transmitting the signal to a quality evaluation unit; the quality evaluation unit adaptively screens the signal and outputs a standard radiation source signal with a radiation source type identifier; and carrying out feature parameter extraction on the standard signal to obtain a multivariate signal feature set, and carrying out multi-band signal fusion and target positioning analysis based on the feature set to generate target position information. According to the invention, the technical problems of complex signal processing, insufficient positioning precision and limited dynamic monitoring capability of the existing passive radar technology in a complex electromagnetic environment are solved, and multi-band signal fusion and adaptive signal processing are realized. And the positioning precision and the dynamic monitoring capability of the passive radar in a complex environment are improved.

The invention relates to a nuclear power plant emergency facility residence judgment method and system, a storage medium and electronic equipment. The nuclear power plant emergency facility residence judgment method comprises the steps that a nuclear power plant emergency facility residence judgment mode is determined according to a selection instruction; the residence judgment mode comprises any one or more combinations of a radiation monitoring-based mode, an accident source item-based mode and an air sampling-based mode; if the judgment mode is any one, a residence judgment result and / or a protection action suggestion are / is given based on the selected judgment mode; and outputting a target residence judgment result and / or a target protection action suggestion based on the residence judgment results of the multiple combinations if the target protection action suggestion is the multiple combinations. According to the method, external irradiation can be judged, contribution of an internal irradiation path can be evaluated, an automatic mode is adopted, the judgment efficiency is improved, human errors can be avoided, the reliability and accuracy of a judgment result are improved, and the reasonability of personnel protection action decisions in emergency facilities is improved.

The present invention belongs to the technical field of radioactive target decontamination, and particularly relates to a target contamination removal and sampling device for decontaminating and sampling a radioactive target (4) inside a glove box. The device includes a clamping mechanism and a wiping mechanism mounted on a rectangular system chassis (1). The clamping mechanism is used to fix the cylindrical target (4), and the wiping mechanism is used to wipe the target (4). In the decontamination and sampling operations of the target, the present invention reduces the finger tip dose and the whole body external irradiation dose of the operator, improves the decontamination effect, and simplifies the operation.

The invention provides an off-site radiation dose evaluation method and device based on nuclide migration joint simulation, and the method comprises the steps: obtaining the working condition data and meteorological data of a nuclear power plant; based on the working condition data and the working condition judgment condition, identifying a target release working condition to which the nuclear accident belongs; determining key radionuclides based on the target release working condition; based on the working condition data, the meteorological data and the environmental data of the emergency planning area corresponding to the nuclear power plant, obtaining the total irradiation dose of the key radionuclide through an airborne radionuclide migration dose model, a water radionuclide external irradiation dose model and a soil deposition external irradiation dose model, the technical problems in the prior art are solved.

The invention discloses a train flame-retardant material fire spreading experiment device and an experiment method, relates to the technical field of flame-retardant material experiments, and solves the technical problem that the authenticity of a fire spreading process is affected due to the fact that an existing experiment device is difficult to simulate a gradually-changed heat radiation area at present. The device comprises a sample fixing assembly, a heat radiation shielding assembly and an external heat radiation assembly which are sequentially arranged from bottom to top, the upper portion of the heat radiation shielding assembly is fixed to the lower portion of the external heat radiation assembly, and the sample fixing assembly is used for clamping and fixing different types of flame-retardant material test pieces; the external heat radiation assembly is used for simulating an external radiation heat source, and the heat radiation shielding assembly is used for controlling the exposure time and the exposure area of the external heat radiation assembly; the objective of the invention is to realize active and accurate regulation and control of key influence factors in the fire spreading process.

The utility model discloses a laser film UV printing part, which relates to the technical field of processing equipment and comprises a drying processing box and a film material, and a plurality of external irradiation lamp bodies are arranged on two sides of the inner wall of the drying processing box. An upper material guide roller in the drying treatment box and a bearing frame at the bottom of the drying treatment box are matched with driving equipment for use to drive a film material to pass through the drying treatment box, and at the moment, external irradiation lamp bodies on the inner walls of the two sides in the drying treatment box can perform curing irradiation on the outer surface of the film material when the film material moves in the drying treatment box; the inner irradiation lamp body is arranged in the drying treatment box, so that the inner surface of the film material can be cured and irradiated when the film material moves in the drying treatment box, and the printing ink permeating from the upper surface to the lower surface can be quickly dried; and when the film material enters the drying treatment box and then comes out of the drying treatment box, the advancing time can be prolonged.

The application belongs to the technical field of biological medicine, and particularly relates to an ultrathin radioactive patch for skin cancer treatment and a preparation method thereof. The preparation method comprises the following steps: adding a photoinitiator solution into a methyl methacrylate gelatin solution, and performing water bath heating dissolution under light shielding conditions; after the dissolution is completed, mixing the radioactive particles used for external irradiation treatment, stirring to a semi-solid state, smearing to a patch bottom film by using a smearing part, covering the patch anti-adhesion paper on the surface, irradiating and curing by using a light source, and obtaining the ultrathin radioactive patch. The patch prepared by the application can be customized according to the size and shape of a lesion site, a corresponding bottom film is cut out and attached to the lesion site, and smearing is directly performed. Compared with a common radioactive hydrogel, the preparation method is simpler, the preparation time is shorter, and the efficiency is higher.

The invention discloses a finite box rectangular horn shape optimization method and system based on a hybrid model, and the method comprises the steps: carrying out the geometric discretization of a rectangular horn in the axial direction into rectangular pipeline sections which are connected end to end, and determining a to-be-optimized design variable; pre-calculating a radiation impedance matrix and a far-field directivity primary function vector under a finite box body by adopting an external radiation model; calculating an inlet impedance matrix and a speed transmission matrix of each rectangular pipeline section on the basis of a radiation impedance matrix and a current design variable by adopting a sound transmission model in the horn, obtaining a mouth output speed vector, and solving an acoustic performance index in combination with a far-field directivity primary function vector; and constructing a comprehensive objective function, and solving to obtain a finite box rectangular horn shape optimization scheme. According to the method, the edge diffraction and sound reflection effect in a limited box environment can be accurately simulated, and the radiation efficiency optimization and directivity control of the broadband of the rectangular horn are realized while the calculation cost is remarkably reduced.

The invention belongs to the technical field of biomedical nano-drugs, and discloses a radionuclide-labeled nano combined therapeutic agent with radiosensitization and a preparation method and application thereof, the bismuth oxyiodide nano combined therapeutic agent comprises a nano-particle carrier and radionuclides distributed in crystal lattices of the nano-particle carrier; the nano-particle carrier is bismuth oxyiodide of which the surface is coated with polyvinylpyrrolidone with negative charges; and the radionuclide adopts nuclide with a short half-life period. According to the invention, short-half-life nuclide is efficiently loaded through the bismuth oxyiodide BiOI nano-carrier, and a novel efficient and low-toxicity radiopharmaceutical strategy is provided for tumor treatment by combining radiation sensibilization and external irradiation synergism.

A reactor device comprises a reaction vessel for receiving at least one medium, whereinthe reactor device comprises an external irradiation unit that is arranged outside the reaction vessel, with at least one external radiation element, for an irradiation of the medium within the reaction vessel.

1. The name of the design product: house (chest examination safety cabin). 2. The use of the design product: used for isolating external radiation leakage and placing chest examination equipment. 3. The design points of the design product: in shape. 4. The picture or photo that can best show the design points: perspective view.

The invention relates to an insulator defect grading method based on external source irradiation and solar blind detection, which comprises the following steps: irradiating the surface of an insulator through a short wave external light source pulse, carrying out solar blind ultraviolet photon detection in a discharge active period after irradiation, and grading defects through an ultraviolet photon number measurement result. Therefore, traditional passive discharge detection is converted into active controllable detection.

New techniques for remote administration of medicine and medical devices using an external guidance and activation system are provided. In some embodiments, medicine(s) and / or medical device(s) is / are energized to a predetermined threshold energy level by externally applied radiation, and then driven into the treatment target. The design of such device(s) (e.g., injectable machine(s)) may include sub-device(s), e.g., medical payload-carrying reservoir(s), injector(s) and abrasive tool(s), which may be activated magnetically and / or by such radiation. In some aspects, such sub-device(s) include actuable housing(s) and / or other sub-tool(s), delivering drugs to specific locations commanded by a control system or a user. In other aspects, a medicine and / or device is provided with multiple dipoles, each oriented differently in three-dimensional space, allowing a guidance control system, remote from the medicine or device, to drive the movement and three-dimensional orientation of the medical agent or particle according to a three-dimensional path.

Disclosed are a β-ray therapy apparatus and a use method therefor. The present invention pertains to the field of nuclear medicine external irradiation therapy. The apparatus comprises a therapy apparatus body and a conformal structure. The therapy apparatus body comprises a β-ray source and a β-ray shielding structure. A mounting cavity and a window communicating with the mounting cavity are arranged on the β-ray shielding structure, and the β-ray source is mounted in the mounting cavity. The conformal structure comprises a conformal frame and a plurality of conformal sheets. A transmission area is arranged in the middle of the conformal frame. The conformal sheets are arranged on the conformal frame and can move toward or away from the transmission area. The positions of the conformal sheets are adjusted to form a conformal area surrounding a part to be treated in the transmission area. The β-ray source emits β-rays toward the conformal area through the window. In the present invention, conformal areas having different shapes can be formed on the basis of parts to be treated having different shapes, and the parts to be treated are then irradiated with β-rays emitted by the β-ray source through the conformal area. The present invention can use one therapy apparatus to match parts to be treated having different shapes, showing universality and adjustability.

The invention relates to a thermal image capture system comprising: - a housing (110) defining a first opening; - a window (120) configured to at least partially cover the first opening; and - a capture device (130) positioned inside the housing and comprising a sensor (131) and an outer casing (132), wherein the outer casing accommodates the sensor and defines a second opening. The window, the first opening, and the second opening are positioned so as to allow external radiation through to the sensor. According to the invention, the thermal image capture system comprises a thermal interface (140) positioned so as to be in contact with the window and in contact with the capture device, wherein the thermal interface defines a third opening configured to allow the external radiation through to the sensor and to define, together with the window and the capture device, a sealed space containing a gas layer.

This invention discloses a puncture device and puncture system, including a puncture needle mechanism, a linearly movable moving mechanism, and a clamping mechanism for supporting the puncture needle mechanism. The moving mechanism includes a base, a sliding component, and a puncture driving component. The sliding component is slidably disposed on the base. The puncture driving component includes a shielding box for shielding external radiation and a puncture driving member. The shielding box is connected to the base, and the puncture driving member is built into the shielding box and connected to the sliding component, used to drive the sliding component to move linearly relative to the base. The clamping mechanism includes a first clamping component and a clamping driving component. The first clamping component is disposed on the sliding component, and the clamping driving component is built into the shielding box and connected to the first clamping component, used to drive the first clamping component to clamp or release the puncture needle mechanism. This invention eliminates the need for manual operation of the puncture needle for puncture.

The present disclosure relates to an automatable measuring device 100 applicable to any electromagnetic radiation source 200, in particular a vehicle headlight during a headlight test, as well as a system and a method which make it possible to reconstruct the four-dimensional electromagnetic radiation field of the radiation source 200 by consecutively capturing restricted light beams of the radiation source 200 to be analyzed, and thus to provide an efficient, cost-effective and extremely precise measuring mechanism for determining any radiation pattern deviations.

Apparatuses, systems and methods are disclosed for reducing interference between an active illumination device and external radiation sources, for example, other active illumination devices operating within the vicinity. A disclosed system includes one or more active illumination devices, each configured to emit an illumination signal and also to receive a returned portion of its respective illumination signal with at least one sensor. At least one of the active illumination devices is capable of detecting interference caused by an external source, for example, an illumination signal emitted from another active illumination device. As a result of detecting the interference, the receiving active illumination device changes the timing of its subsequent illumination signals and sensor operation. By detecting collisions between illumination signals and consequently altering the timing of it operation, the active illumination device may reduce interference in congested environments where multiple active illumination devices are operating within range of each other.

The invention relates to a radioactive gas extraction device with an external irradiation shielding function and a manufacturing and using method thereof. The device comprises a shell (1), a gas guide joint nut (2), a gas guide tube (3), a gas outlet joint (4), a gas outlet joint nut (5), a heating layer (6) and an external shielding layer (7), a radioactive gas to-be-extracted product is arranged in the shell (1), the gas guide connector nut (2) is communicated with the interior of the shell (1) through the gas guide pipe (3), the gas outlet connector nut (5) is communicated with the interior of the shell (1) through the gas outlet connector (4), and a heating layer (6) and an outer shielding layer (7) are sequentially arranged on the outer side of the shell (1). Compared with the prior art, the external radiation shielding function of the device is expected to achieve the effects of a traditional extraction hot chamber and an extraction furnace, and meanwhile, conditions can be created for continuous extraction of radioactive gas.

The invention belongs to the technical field of radiation environment monitoring, and particularly relates to a collecting device and method for radioactive slurry samples in a tank body, the device comprises a collecting end capable of extending into the tank body to collect the radioactive slurry samples, and the collecting end comprises a sample tank (2) and a one-way valve (3) arranged at a port of the bottom end of the sample tank (2). According to the collecting device and method, efficient, accurate and safe collection of the radioactive slurry sample in the tank body can be achieved, the stability and repeatability of a sampling result are ensured by matching with a collection program of standardized design, the sample collection program is simplified while it is ensured that sample collection has representativeness, the labor cost is reduced, and the working efficiency is improved. And the external irradiation dose of workers is effectively guaranteed.

A thermal imaging capture system is proposed comprising: - a housing (110) defining a first aperture, - a window (120) configured to at least partially cover the first aperture, and - a capture device (130) positioned inside the housing and comprising a sensor (131) and an outer casing (132), the outer casing housing the sensor and defining a second aperture. The window, the first aperture, and the second aperture are positioned to allow external radiation to pass to the sensor. According to the invention, the thermal imaging capture system includes a thermal interface (140) positioned to be in contact with the window and with the capture device, said thermal interface defining a third aperture configured to allow said external radiation to pass to the sensor and to define, with the window and the capture device, a sealed space containing a gas layer.Figure for the abridged version: Fig. 1.

The invention belongs to the technical field of medical detection, and discloses a method and system for quantifying the relative bioavailability of the internal irradiation dose of a nuclide drug, and the method comprises the steps: dividing the same batch of experimental animals carrying tumors into two groups, and respectively carrying out the internal irradiation of a to-be-detected treatment nuclide drug and the external irradiation of a contrast nuclide drug, radiation damage information and / or radiation response information of the two groups of experimental animals are / is obtained, then the two groups of information are compared, dose pairing is carried out, and finally the relative bioavailability of the internal irradiation dose of the to-be-detected nuclide drug is calculated. The defects that in the prior art, the biological effect of nuclide medicine internal irradiation treatment is greatly different from that of traditional external irradiation radiotherapy, and a means for effectively quantifying the relative bioavailability of the nuclide medicine internal irradiation dose is lacked are overcome. The relative bioavailability of the irradiation dose in the nuclide medicine can be accurately quantified, and a scientific basis is provided for research, development and clinical application of targeted radiopharmaceuticals.

The invention relates to a high-protection low-gravity-sense external irradiation protective garment which comprises an exoskeleton module and a protective garment module, when the protective garment is worn, the exoskeleton module is arranged on the inner side of the protective garment module, the exoskeleton module comprises a shoulder supporting part, a length adjusting part and a weight transferring part, and the weight transferring part is arranged on the shoulder supporting part by adjusting the length adjusting part of the exoskeleton module. Therefore, each joint position of the exoskeleton module corresponds to the joint position of the human body, and meanwhile, a preset height gap is kept between the shoulder supporting piece of the exoskeleton module and the shoulder of the person, so that the shoulder supporting piece of the exoskeleton module is prevented from being in direct contact with the shoulder of the human body; the exoskeleton module directly supports the protective clothing module through the shoulder supporting piece and carries out load transfer through the weight transfer component. The lead equivalent of the external irradiation protective clothing can be effectively improved, the ray protection effect can be greatly improved, the protection requirement of personnel in high-dose-rate places is met, meanwhile, the body load of shielding materials of the protective clothing on wearers is relieved, and the working efficiency is guaranteed.

The application provides an off-site radiation dose evaluation method and device based on nuclide migration combined simulation. The method comprises the following steps: acquiring working condition data and meteorological data of a nuclear power plant; identifying a target release working condition to which a nuclear accident belongs based on the working condition data and a working condition judgment condition; determining a key radioactive nuclide based on the target release working condition; and obtaining total irradiation dose of the key radioactive nuclide through an air-borne radioactive nuclide migration post-dose model, a water body radioactive nuclide external irradiation dose model and a soil deposition external irradiation dose model based on the working condition data, the meteorological data and environmental data of an emergency plan area corresponding to the nuclear power plant, so as to solve the technical problems in the prior art.