88 results about "Radiation level" patented technology

The invention relates to the technical field of radiation early warning, in particular to an ambient radiation influence early warning system for a proton treatment system. The system comprises a radiation monitoring data acquisition module, a radiation space distribution generation module, a radiation risk level determination module, a radiation leakage analysis module, a risk information dynamic notification module and a treatment optimization suggestion module. According to the invention, through real-time monitoring and data integration of the radiation monitoring environment, the response speed and accuracy of radiation safety early warning are improved, and a detailed radiation distribution diagram can be constructed by using spatial data and radiation intensity information, so that risk assessment is more visual and easy to understand; the accurate assessment of the radiation risk allows specific and targeted protection measures to be taken, the potential leakage points are classified according to the radiation level deviation, the risk information is dynamically reported, it is ensured that the therapeutic personnel can receive key safety alarms in time, the therapeutic process is optimized, and the radiation risk of the patient is reduced.

The embodiment of the invention provides a dual-polarization indoor distribution antenna, and belongs to the antenna communication equipment technology, the dual-polarization indoor distribution antenna comprises a vertical polarization radiation unit and a horizontal polarization radiation unit, the vertical polarization radiation unit comprises a grounding plate and a conical radiation oscillator arranged on the grounding plate, the conical radiation oscillator is used for being excited to radiate vertical polarization electromagnetic waves; the horizontally polarized radiation unit comprises a plurality of radiation subunits, the plurality of radiation subunits are sequentially arranged around the peripheral side of the conical radiation oscillator, a radiation gap is formed between every two adjacent radiation subunits, and the radiation gaps are used for being excited to radiate horizontally polarized electromagnetic waves; the orthographic projection of the radiation subunit on the grounding plate is located in the grounding plate. According to the dual-polarization indoor distribution antenna provided by the embodiment of the invention, broadband coverage can be realized, and the multi-band requirement of an indoor communication system is met.

The invention discloses a transmitting power configuration method and device, equipment, a storage medium and a product, and relates to the technical field of communication, and the method comprises the steps: determining a unified upper limit transmitting power according to a target overall electromagnetic radiation level value and a total number; generating a target power coordination strategy of each antenna according to the current application scene; and adjusting the unified upper limit transmitting power according to each power coordination strategy, and configuring the adjusted upper limit transmitting power for the corresponding antenna. Through the mode, the unified upper limit transmitting power is determined according to the target overall electromagnetic radiation level numerical value and the total number, and then the target power coordination strategy is generated according to the current application scene, so that an isolation decision mode among the communication units in the target communication module is broken, unified power management among the multiple communication units is realized, and the communication efficiency is improved. And then the adjusted upper limit transmitting power is configured for the corresponding antenna, so that the transmitting power configuration accuracy can be effectively improved, and the dual requirements of communication experience and compliance are ensured.

The invention belongs to the technical field of nuclear facility decommissioning and three-waste treatment, and particularly relates to an automatic laser decontamination system and method for polluted metal waste of a nuclear power plant. The decontamination / cutting workbench is transferred to all stations and an operation table through a transfer trolley; the operation table is used for controlling the transfer of the transfer trolley, controlling the operation of the workpiece turnover device, measuring the size of a to-be-decontaminated item and measuring the surface contamination level and radiation level of the to-be-decontaminated item before and after decontaminating; and the controller is used for recording a measurement result, presetting cutting parameters and decontamination process parameters of a to-be-decontaminated item, and controlling the laser cutting device, the laser cleaning device and the laser stripping device to carry out laser cutting and automatic laser decontamination operation. According to the invention, the labor intensity of personnel can be effectively reduced, the exposure dose of the personnel is reduced, the decontamination working efficiency is improved, waste degradation or clean control of surface polluted metal waste is realized, and waste minimization is further realized.

This application provides a communication method, apparatus, storage medium, and computer program product. The communication method includes: in response to the influence of the Maximum Allowable Radiation Level (MPE) on a terminal device, recording radiation impact information caused by the MPE; receiving a first Radio Resource Control (RRC) reconfiguration message from a source base station; recording a measurement report from the terminal device; and sending the measurement report and the radiation impact information to the source base station. Using this application embodiment can reduce the impact of MPE on mobility and improve the handover success rate.

The present invention discloses an adaptive vehicle-mounted γ radiation patrol and survey system, which includes a γ radiation patrol and survey device, an adaptive adjustment bracket, and a result analysis module. The γ radiation patrol and survey device is installed on the adaptive adjustment bracket, and the γ radiation patrol and survey device is communicatively connected to the result analysis module; an adaptive vehicle-mounted γ radiation patrol and survey system has a reasonable measurement height, strong adaptability, a fast response speed of the γ radiation measurement device, accurate γ radiation measurement results, higher cooperation efficiency for multiple sets, can simultaneously display real-time patrol and survey trajectories and results, and can real-time produce γ radiation level isoline maps of emergency areas, providing real-time pollution situation and decision-making suggestions for nuclear and radiation accident emergencies; it has significant efficiency advantages during large-scale regional radiation patrol and survey.

The present invention belongs to the technical field of controlling the source term of radioactive anions in a primary circuit during a refueling overhaul of a nuclear power plant, and specifically relates to a system and method for purifying radioactive anions Sb-124 in a nuclear power plant. The system comprises: a primary circuit main pipeline, a reactor special drainage system, a chemical and volume control system degasser, and a primary circuit coolant temporary storage system. The primary circuit main pipeline is connected to the chemical and volume control system degasser via the reactor special drainage system, the chemical and volume control system degasser is connected to the primary circuit coolant temporary storage system to purify the Sb-124 nuclide, and the primary circuit coolant temporary storage system is connected to the primary circuit main pipeline to achieve closed-loop purification of the Sb-124 nuclide. The present invention can reduce the primary circuit Sb-124 radiation source term, reduce the radiation level in the maintenance area, and reduce the radiation exposure dose to personnel.

The utility model provides a radioactive source shell which comprises a source cover and a source frame installed together with the source cover, and an inner cavity is formed inside the source cover and the source frame. The radioactive source and the shielding column are placed in the inner cavity, and the shielding column is located above the radioactive source. The utility model further provides a radioactive source container which comprises the radioactive source shell and further comprises a barrel body composed of a barrel body bottom plate, an outer barrel body and a barrel body upper cover. A shielding layer is wrapped in the barrel body, and the radioactive source shell is arranged in the shielding layer in the barrel body; and the upper part of the barrel body upper cover is also covered with a cover. According to the radioactive source shell, the length of the source frame is shortened, the shielding columns are additionally arranged, the length of the source cover is increased, the shielding effect of the top of a container is improved, after the radioactive source shell is placed in the radioactive source container, shielding bodies are arranged on the periphery, the upper portion and the lower portion of a radioactive source, and meanwhile radiation levels in all directions of the periphery of the container are almost consistent.

The invention discloses a method and system for evaluating and forecasting water-wind-solar complementary characteristics based on grading. The method comprises the following steps: acquiring historical meteorological data of continuous multiple days in a target area; the meteorological data comprises wind speed, total radiation and precipitation; according to the wind speed, the total radiation and the precipitation of multiple days, the quartile, the average value and the positive and negative two-time standard deviation of the wind speed, the total radiation and the precipitation of multiple days are calculated, and according to the quartile, the average value and the positive and negative two-time standard deviation of the wind speed, the total radiation and the precipitation of multiple days, the average value and the positive and negative two-time standard deviation are calculated. Calculating division intervals of different grades of wind, light and water according to different grades of wind, light and water power generation efficiency; future forecast meteorological data are obtained, and grades corresponding to future wind speed, total radiation and precipitation are calculated according to different grades of divided intervals of wind, light and water; and adding the future forecast wind speed grade, the current day total radiation grade and the future forecast precipitation grade to obtain a complementary characteristic index. According to the invention, the water-wind-light complementary characteristic index can be accurately evaluated and forecasted.

This invention relates to the field of radiation early warning technology, specifically to an early warning system for the radiation impact on the environment surrounding a proton therapy system. The system includes a radiation monitoring data acquisition module, a radiation spatial distribution generation module, a radiation risk level determination module, a radiation leakage analysis module, a dynamic risk information notification module, and a treatment optimization suggestion module. In this invention, by real-time monitoring and data integration of the radiation monitoring environment, the response speed and accuracy of radiation safety early warning are improved. By utilizing spatial data and radiation intensity information, a detailed radiation distribution map can be constructed, making risk assessment more intuitive and easier to understand. Accurate assessment of radiation risk allows for specific and targeted protective measures, and potential leakage points are classified according to radiation level deviations. Dynamic notification of risk information ensures that treatment personnel receive critical safety alerts in a timely manner, optimizing the treatment process and reducing the radiation risk to patients.

A system for monitoring ultraviolet (UV) exposure of a wearer. The system comprises a wearable device operable to sense UV radiation levels to which the wearer is exposed, and to transmit UV radiation information. The system further comprises an external computing device in remote communication with the wearable device, operable to receive the UV radiation information from the wearable device and configured to determine the wearer's real-time UV index value and the wearer's daily cumulative percentage of minimal erythema dose based upon the UV radiation information.

Interstitial brachytherapy is a cancer treatment in which radioactive material is placed directly into target tissue at the affected site using a afterloading machine. The accuracy of this placement is monitored in real time using a catheter, which positions the radioactive material based on radiation levels measured by sensors embedded in the catheter wall. A scintillator embedded in the catheter wall produces light when irradiated with the radioactive material. This light is proportional to the radiation level at each location. The light produced by each scintillator is transmitted via optical fiber and then converted into an electrical signal proportional to the light and radiation levels at each location. The location of the radioactive material is determined based on multiple electrical signals. This location can be used as quality control feedback to the afterloading machine.

A method and device for intelligently monitoring and evaluating the radiation protection performance of a hospital's proton therapy area relates to the field of radiation monitoring. The method includes: performing a 3D scan of the actual building structure and equipment layout of a target proton therapy center to obtain 3D scan data, and then modifying a preset BIM model using the 3D scan data to obtain a 3D building model. After the detection equipment is turned on, the measured dose rate level of the target proton therapy center at a preset target measurement point is obtained. The measured dose rate level is curve-fitted to obtain a measured dose rate curve. The simulated dose rate level and the measured dose rate curve are then merged to obtain the actual dose rate level at each building structure location. The actual dose rate level is then mapped onto the 3D building model to obtain a 3D dose distribution map. Implementing this method can more intuitively demonstrate the radiation protection level of a hospital's proton therapy area.

Effective radioactive waste management will be implemented to ensure that radiation levels do not harm the environment or all forms of living organisms. [Solution] An apparatus and method positioned in close proximity to a radiation source to receive radiation from a radioactive material and configured to return the received radiation back to the source comprises at least one reflective means that partially reflects radiation, thereby effectively reducing the leakage of radiation emitted from the radiation source.

The double-station radioactive filter element transfer device comprises a vehicle body, a winding device, a three-jaw automatic centering mechanism and a corrugated pipe sealing sleeve, a shielding case is installed on the vehicle body, and a shielding door is formed in the side face of the shielding case; the interior of the shielding cover and the vehicle body are divided into a first station and a second station, the first station and the second station both comprise round holes formed in the vehicle body, and cover plates are arranged on the round holes; a shielding cylinder is arranged at the position corresponding to the first station. The transferring method comprises the following steps that S1, the shielding cover plate and the shielding plug are hoisted; the new filter element is transferred to a station II; s2, grabbing an old filter element; and S3, replacing the old filter element with a new filter element. By adopting a double-station method, aerosol of the pit filter can be prevented from overflowing in the replacement process, the radioactive sealing containing boundary of the pit filter is guaranteed, the filter element can be rapidly replaced, the shielding cylinder is shielded by a lead layer, and it is guaranteed that the radiation level of personnel is controllable.

The invention relates to the technical field of radiation detection, and particularly discloses a patrolling device for hospital radiation health protection detection, which comprises a detection shell, a radiation detection module, an airborne radioactivity monitoring module, a man-machine interaction module and a control unit are integrated in the detection shell, and the airborne radioactivity monitoring module comprises a detection fan and a specially designed air duct. A cyclone effect can be generated to enrich aerosol, and the control unit adaptively adjusts the rotating speed of the fan according to the real-time radiation level and controls the display light bar and the vibration module to provide visual and tactile alarms matched with the risk level and direction; by arranging the speed-adjustable detection draught fan and the cyclone separation structure, the airflow speed can be dynamically adjusted according to the radiation level, selective enrichment of airborne radioactive substances is achieved, the centrifugal enrichment effect is enhanced by increasing the wind speed under the low-concentration condition, and the detection sensitivity and response speed of equipment to airborne radioactivity are remarkably improved.

The invention discloses a nuclide treatment patient excrement intelligent collection and radiation shielding system and method, and relates to the technical field of nuclide treatment, and the system comprises a data collection module which collects the excrement data of a patient, detects and records the nuclide information in the excrement of the patient, and carries out the data preprocessing; the nuclide analysis module is used for carrying out nuclide type and content analysis on the collected excrement data and outputting a nuclide analysis result; the intelligent collection module intelligently adjusts the working state of the excrement collection system according to the nuclide analysis result; the radiation shielding module is used for shielding radiation generated in the excrement collection process; and the real-time monitoring module feeds back radiation level, excrement amount and nuclide content data in real time. Through intelligent data analysis and real-time feedback, the nuclide type, concentration and radiation level in excrement are monitored, the safety standard is ensured, the container capacity and the collection speed are automatically adjusted, waste is avoided, and the efficiency is improved.

The utility model discloses an annular shielding device for a high-radiation horizontal pipeline, relates to the technical field of ionizing radiation shielding, and is used for solving the problem that the high-radiation horizontal pipeline needs to be quickly shielded in a small-range space. The pipeline annular shielding device comprises a flexible shielding body, the flexible shielding body is filled with flexible radiation protection shielding materials, a hook side of a hook-and-loop fastener is designed at one end of the inner surface of the flexible shielding body, and a fine brush of the hook-and-loop fastener is designed on the outer surface of the other end of the flexible shielding body. The flexible shielding bodies are connected end to end, the hook sides of the hook-and-loop fasteners are adhered to the fine hairbrushes of the hook-and-loop fasteners to form an annular closed body, and pipelines with different pipe diameters are shielded according to different adhering positions between the hook sides of the hook-and-loop fasteners and the fine hairbrushes of the hook-and-loop fasteners.

The invention relates to the technical field of waste treatment, and discloses a nuclear power radioactive waste sorting identification method, which comprises the steps of multi-modal data acquisition, feature fusion and preprocessing, classification and identification algorithm and real-time sorting decision. The radioactive waste sorting identification method comprises the steps of data collection and preprocessing, feature extraction, model training, real-time sorting identification and model updating and maintenance, and a Bayesian algorithm is adopted as a specific classification and identification algorithm. According to the nuclear power radioactive waste sorting and identifying method, through multi-modal data acquisition, comprehensive information, including radiation level, physical characteristics, chemical composition and the like, of radioactive waste can be obtained, so that the waste type is identified more accurately; key information is further extracted in the feature fusion and preprocessing step, noise interference is reduced, and the accuracy of a subsequent classification algorithm is improved.

The application discloses a radiation level monitoring method and system, an electronic device and a storage medium. The method comprises the following steps: collecting first radiation data through a preset radiation monitoring sensor; performing data dimension reduction processing on the first radiation data through a feature dimension reduction model to obtain second radiation data; the feature dimension reduction model comprises a boundary smoothing-based autoencoder; performing data augmentation on the second radiation data through a preset generative adversarial network model to obtain third radiation data; the preset generative adversarial network model comprises a quantum state-based generative adversarial network model; performing model training on a preset monitoring model through a federated learning architecture according to the third radiation data to obtain a target radiation monitoring model; inputting to-be-analyzed radiation data into the target radiation monitoring model for radiation level analysis to obtain a radiation level monitoring result. The embodiment of the application can effectively alleviate the data privacy risk problem and improve the accuracy of radiation level monitoring. The application can be widely applied to the technical field of monitoring.

The application relates to an oral X-ray machine room for a residential building and a design method, a fixed machine room, a closed space composed of M installation surfaces, an oral X-ray machine is internally installed, wherein M is a positive integer, and M is greater than or equal to 6; a partition plate is arranged in the fixed machine room, is parallel to the installation surface, and is spaced apart from the installation surface by at least a distance of a meters, the interval between the partition plate and the installation surface forms a partition layer, wherein a is a natural number greater than or equal to 1; a detection port is arranged on the installation surface and is communicated with the partition layer and the outside of the fixed machine room, and is used for detecting the radiation level in the partition layer through the detection port. The application solves the technical problem that the oral clinic is difficult to normally operate due to the fact that neighbors in the residential building do not cooperate with the radioactive examination.

To provide a method and a video capturing system for controlling an infrared illumination source illuminating an area captured by a camera.SOLUTION: A method comprises the steps of: modulating emission from an infrared illumination source between a first emission intensity and a second emission intensity at a first frequency during a first prescribed period; upon capturing images using an image sensor of a camera during a first predetermined time period, determining a radiation level indicator for each one of a plurality of the images captured by the image sensor; evaluating a sequence of determined radiation level indicators to determine whether a frequency resulting from the modulated emission at the first frequency is detected or not in the sequence of radiation level indicators; and If the evaluation results in the frequency resulting from the modulated emission at the first frequency being determined as not detected in the sequence of radiation level indicators, stopping the infrared illumination source from illuminating the area captured by the camera.SELECTED DRAWING: Figure 4

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.

1. The name of the design product: ionizing radiation dose alarm. 2. The use of the design product: the design product is based on single-chip microcomputer technology, used for real-time monitoring of ionizing radiation (such as X-rays, gamma rays, beta rays, etc.) dose, and issuing an alarm when the radiation level exceeds the preset threshold. It is a portable instrument for ensuring the safety of personnel in a radiation environment. 3. The design points of the design product: in shape. 4. The picture or photo that best indicates the design points: perspective view.

The invention discloses a circularly polarized antenna, and relates to the technical field of antennas. The circularly polarized antenna comprises a dielectric layer, a radiation layer and a grounding layer which are respectively arranged at two sides of the dielectric layer, and a feeder line used for connecting the radiation layer and the grounding layer. The first radiation patch in the circularly polarized antenna can radiate vertical polarized waves, and the second radiation patch can radiate horizontal polarized waves. Because the radiation layer can generate two kinds of polarized waves, the circularly polarized antenna can enhance the overall radiation capability. Moreover, the circularly polarized antenna provided by the embodiment of the invention adopts the coaxial probe for central feeding, and has the advantages of simple structure, low profile, circular polarization, high efficiency and the like.

The invention discloses a decontamination shielding system, a using method thereof and a manufacturing method of a shielding structure. According to the decontamination shielding system, the movable decontamination device provides a decontaminant for decontamination of the radioactive hotspot interception device, the purification and filtration device purifies and filters hotspots washed out by the radioactive hotspot interception device, the shielding structure effectively shields a bent pipeline, and the movable decontamination device, the purification and filtration device and the shielding structure achieve a synergistic effect; the decontamination effect and the shielding performance can be obviously improved. The manufacturing method of the shielding structure is scientific and reasonable, and the quality and performance of the shielding structure are ensured. The use method of the system is simple and convenient, the operability is high, the radiation level of the radioactive hot spot interception device can be effectively reduced, and safe operation of nuclear industry production is guaranteed.

The present application relates to the technical field of nuclear power plants, and particularly relates to a radiation signal monitoring apparatus and method for a nuclear power plant, and an electronic device and a storage medium. The radiation signal monitoring apparatus for a nuclear power plant in the embodiments of the present application comprises a power supply module, a radiation detector, a processing control module, a monitoring indication module and an integrated module, wherein the radiation detector is divided into a low-dose detection branch and a high-dose detection branch, which are respectively equipped with corresponding sensitive elements and signal conditioning modules, so as to adapt to radiation environments having different dose rates; the processing control module is responsible for selecting an appropriate detection branch on the basis of a radiation level, and generating a monitoring indication signal; and the monitoring indication module receives the signals and executes a monitoring response operation. By means of the unified management by an integrated module, effective monitoring of wide-range radiation signals is realized without significantly increasing the complexity and cost of a system. In this way, radiation signals within a relatively wide range can be effectively collected without significantly increasing the complexity and cost.

The utility model discloses a nuclear waste transportation device, which belongs to the technical field of radioactive nuclear waste transportation and comprises an outer box body and a shielding box body arranged in the outer box body, and the shielding box body is attached to the outer box body and used for shielding radioactivity of a nuclear waste storage barrel. The shielding box body comprises a cover body and a shielding box body, and a locking device is arranged at the top end of the cover body and used for locking and connecting the cover body and the shielding box body. According to the nuclear waste transportation device, the shielding box body structure matched with the common YA-II steel box in size is arranged in the common YA-II steel box, the shielding box body can be loaded with ten waste bins with the maximum size of 400 L, then the requirement for the radiation level in related standards can be met, and the safety of the waste bins in the shielding box body in the transportation process can be guaranteed.

An electrochemical-deposition apparatus includes an electrode array, a photoconductor, an electrically conductive layer, an electromagnetic-radiation emitter, an electric-power source, and a controller. The controller is configured to direct electric power to be supplied from the electric-power source to the electrically conductive layer and direct the electromagnetic-radiation emitter to generate electromagnetic radiation. When the electric power is supplied to the electrically conductive layer and when the electromagnetic radiation is generated, the photoconductor is illuminated at a first radiation level and a first level of electric current is enabled through the photoconductor and the at least one deposition electrode. When the electric power is supplied to the electrically conductive layer and when the electromagnetic radiation is generated, the photoconductor is illuminated at a second radiation level and a second level of electric current is enabled through the photoconductor and the at least one deposition electrode.

A method and a video capturing system for controlling at least one infrared (IR) illumination source, illuminating an area captured by a camera, the method comprising modulating emission from the IR illumination source between first and second emission intensities at a first frequency during a first predetermined time period. Upon capturing images using an image sensor of the camera during the first predetermined time period, determining a radiation level indicator for each of a plurality of images captured by the image sensor. Further, evaluating a sequence of determined radiation level indicators to determine whether a frequency resulting from the modulated emission at the first frequency is detected in the sequence of radiation level indicators. If the frequency resulting from the modulated emission at the first frequency is determined as not detected in the sequence of radiation level indicators, the IR illumination source is stopped.