356 results about "Radioactive agent" patented technology

The invention discloses a radioactive substance multi-point synchronous detection and identification method and system, and relates to the technical field of radioactive substance monitoring. Comprising the following steps: step 1, collecting multi-point radiation data in real time, and preprocessing and storing the data; step 2, constructing a spatial adjacency matrix, estimating a local spatial gradient, calculating an anomaly degree value, taking optimization measures, and performing collaborative anomaly evaluation on the monitoring nodes; 3, calculating a total fitting error value, reversely deducing a leakage source position and leakage intensity in real time, and taking corresponding measures in real time; 4, abnormal trend identification is carried out, an early warning judgment value is calculated, and graded early warning and multi-node cross confirmation measures are implemented; and 5, receiving and storing various types of data, carrying out visualized analysis on the data, and supporting event processing and feedback. The problems that due to the fact that some devices are good in shielding and have physical obstruction, trace leakage is difficult to detect by a single-point monitor, and the risk of long-term retention pollution exists are solved.

The invention provides an intelligent sorting method and system for radioactive substances. The method comprises the following steps: synchronously detecting surface element composition and radiation intensity of a radioactive substance through an X-ray fluorescence spectrometer, and constructing a spatial difference matrix of element abundance distribution and a radiation gradient topological graph; the three-dimensional coordinates, the pressure threshold value and the shape adaptation parameters of the target grabbing position are determined on the basis, the curvature radius of the clamping jaw deformation contour is dynamically adjusted, and the error of the dynamic geometric envelope and the contour template is converged to be within the threshold value; finally, when the clamping jaw reaches a target position, the area of the heat shrinkage material is activated to be heated according to the radiation intensity abrupt change boundary coordinates, a sealed isolation layer synchronously expanded with the dynamic geometric envelope is generated, and safe grabbing and sealed isolation of radioactive substances are achieved. According to the technical scheme, accurate grabbing of radioactive substances, error self-adaptive compensation and synchronous isolation of radiation leakage can be achieved, and the sorting safety and efficiency are improved.

The invention discloses a nuclear leakage radioactive substance diffusion situation inversion method and device, and relates to the technical field of nuclear emergency response. The method comprises the following steps: acquiring initial source item parameters and meteorological data, and obtaining a nuclide concentration predicted value through a Gaussian puff model according to the initial source item parameters and the meteorological data; acquiring a nuclide concentration observation value corresponding to the nuclear leakage area, and performing Kalman filtering fusion processing according to the nuclide concentration prediction value and the nuclide concentration observation value to obtain a nuclide optimal concentration field and analysis error distribution; adjusting parameters of a Gaussian diffusion mode according to the analysis error distribution to obtain an adjusted Gaussian diffusion mode, and obtaining target source item parameters based on the adjusted Gaussian diffusion mode and the optimal concentration field; and performing iteration by taking the target source item parameter as an initial source item parameter until a preset requirement is met, and taking the source item parameter obtained when iteration is ended as a final source item parameter. The method can dynamically respond to the sudden change of atmospheric stability, and improves the prediction precision of the nuclear hazard area range.

The utility model relates to a nuclear power high-radiation object containing device and containing and transferring equipment. The containing and transferring equipment comprises the nuclear power high-radiation object containing device. The nuclear power high-radioactivity storage device is specially designed for underwater operation, and can safely store and seal high-radioactivity waste under the condition that normal operation of a reactor is not affected. The sealing mechanism ensures that the radioactive substance storage space is completely sealed in the transferring and long-time storage process, radioactive substances are prevented from leaking, and the safety of the treatment process is greatly improved. And secondly, the torque input end allows torque to be input through an external tool to achieve rotation of the lock cylinder, so that the closing or opening action is rapidly and effectively completed, the operation process of containing and closing the radioactive substances is simplified, and the containing and closing efficiency of the radioactive wastes is improved.

The invention provides an online monitoring device for multiple nuclides in liquid effluent, and particularly relates to the technical field of radioactive substance detection. The online monitoring device comprises a shell, a cascade separation module, a fluid control module, a detection module and a control system, the cascade separation module, the detection module and the control system are arranged in the shell, the cascade separation module comprises a plurality of resin columns and a plurality of separated liquid collecting bottles communicated with the resin columns, and the separated liquid collecting bottles are communicated with the resin columns. The fluid control module comprises a liquid storage device, an injection pump and a control valve, the liquid storage device is respectively communicated with the plurality of resin columns through pipelines, the injection pump and the control valve are respectively arranged on the pipelines and are used for controlling the flow direction and the flow velocity of fluid in the liquid storage device, and the detection module is used for detecting the radioactive activity of nuclide; the control system is used for controlling operation of the cascade separation module, the fluid control module and the detection module. According to the invention, synchronous monitoring of multiple nuclides is realized, the multi-nuclide monitoring efficiency is improved, and the monitoring cost is reduced.

The embodiment of the invention provides an assessment method and device for nuclear power off-site radioactive substance release influence, and belongs to the technical field of nuclear power. The method comprises the following steps: acquiring an evaluation range for evaluating the release influence of radioactive substances, wherein the radioactive substances are released in a smoke plume form; within a preset evaluation duration, simulating the generation and movement process of the smoke plume within the evaluation range according to the meteorological condition of the release site, and obtaining the accumulated concentration and settlement concentration of the smoke plume; calculating according to the accumulated concentration and the settlement concentration to obtain the dose of air immersion external irradiation, the dose of surface external irradiation and the dose of suction internal irradiation in the evaluation range; and performing radiation evaluation according to the dose of the air immersion external irradiation, the dose of the surface external irradiation and the dose of the suction internal irradiation to obtain an evaluation result. According to the embodiment of the invention, migration, settlement, diffusion and other phenomena of the radioactive smoke plume in different areas outside the field can be tracked, influences of meteorological condition changes and settlement are coupled, and the accuracy of an evaluation result is improved.

The invention relates to the technical field of modeling, in particular to a multi-mode imaging and three-dimensional laser scanning fused radioactive distribution modeling method. The method comprises the following steps: performing multi-angle detection on target three-dimensional space radioactive substances based on radioactive detection equipment to obtain a radioactive substance distribution two-dimensional image set; based on a laser scanning device, collecting three-dimensional point cloud data of a target three-dimensional space, assembling the three-dimensional point cloud data, and constructing a target three-dimensional space 3D model; based on the radioactive substance distribution two-dimensional image set, reducing a distribution image of the radioactive substance in the target three-dimensional space by adopting a statistical reconstruction algorithm; and based on the target three-dimensional space 3D model and the distribution image, combining to obtain a radioactive substance three-dimensional distribution modeling result. The technical effect of visually and accurately displaying the distribution condition of the radioactive substances in the three-dimensional space is achieved.

The invention provides a multi-nuclide automatic separation and detection system and method, and particularly relates to the technical field of radioactive substance detection. The detection system comprises a cascade separation and regeneration unit, a dynamic regulation and control unit, an online detection unit, an eluent conveying unit and a control system, and the eluent conveying unit is matched with the cascade separation and regeneration unit to separate and purify radionuclide and regenerate resin. The dynamic regulation and control unit is used for controlling a flow path between the eluent conveying unit and the cascade separation regeneration unit and feeding back changes of pressure, temperature and pH value in the flow path in real time, and the online detection unit is used for detecting concentration of nuclides in separation liquid and feeding back monitoring data to the control system. And the control system controls the operation of each functional unit and automatically plans a separation path according to a measurement requirement to form a separation-detection-optimization closed-loop process. The device is suitable for the fields of nuclear facility liquid effluent detection, environmental water radioactivity detection and the like, and has high efficiency, environmental protection property and intelligence.

To provide a radiopharmaceutical production apparatus and the like capable of reducing the generation amount of radioactive waste.SOLUTION: A radiopharmaceutical production apparatus 51 comprises: a cassette 20 which has a reagent supply port, a radionuclide supply port, a drug solution outlet, a reaction unit, a purification column, and flow paths respectively connecting the reagent supply port and the reaction unit, the radionuclide supply port and the reaction unit, the reaction unit and the purification column, and the purification column and the drug solution outlet; and a cassette mounting unit to which the cassette 20 is attachable and detachable.SELECTED DRAWING: Figure 3

To provide a container dismantling device which improves workability of container dismantling work.SOLUTION: A container dismantling device for dismantling a container contaminated with radioactive substances is provided, the device comprising a base supported at the bottom inside the container, a support member disposed along a vertical direction and supported by the base at a bottom thereof, and a cutting device supported by the support member in such a way that the cutting device is movable along the vertical direction and movable in the circumferential direction.SELECTED DRAWING: Figure 2

The invention discloses a diabase tailing geopolymer cementing material and a preparation method thereof, and belongs to the technical field of building materials. The diabase tailing geopolymer cementing material provided by the invention is prepared from the following components in parts by mass: 80 to 120 parts of diabase tailings, 10 to 20 parts of sodium hydroxide, 80 to 120 parts of water glass, 10 to 20 parts of aluminum hydroxide, 1 to 3 parts of a water reducing agent and 2 to 11 parts of a stabilizing material, the geopolymer cementing material is prepared from the solid waste diabase tailings, harmful solvents, heavy metals and radioactive substances are not added, waste can be turned into wealth, the preparation process is simple, the cost is low, the energy consumption is small, and an effective way is provided for comprehensive utilization of the diabase tailings.

To provide a method for recovering a drying operation in drying of an adsorbent in an adsorption tower capable of preventing movement of the adsorbent downstream during restoration of a drying operation after stop of drying the adsorption tower and thereby enhancing safety.SOLUTION: A method for recovering a drying operation, in which a vacuum pump 13 is connected downstream of an adsorption tower 10 via piping to reduce pressure inside the adsorption tower 10 by sucking air containing water vapor W1, for restoring, upon stop of a drying operation for drying an adsorbent in an adsorption tower 10 that adsorbs radioactive substances contained in contaminated water, includes: restarting the vacuum pump 13 so that the internal pressure of the adsorption tower becomes a set degree of vacuum on the basis of an operating condition under which the adsorbent inside the adsorption tower 10 does not flow; and the vacuum pump 13 operating for a running time of 45 minutes or more and 60 minutes or less from the start of the restart so that the internal pressure of the adsorption tower becomes 2.4 kPa.SELECTED DRAWING: Figure 1

The invention provides a test method and equipment for characterizing etching sediment distribution, and the method comprises the steps: arranging a sampling cabin on the side wall of an etching chamber, and placing a sampling piece in the sampling cabin; introducing radioactive isotope labeled etching gas to carry out an etching process; and performing radioisotope imaging analysis on the sampling piece to obtain distribution data of the etching sediment. The radioactive isotope labeled sediments are collected through the sampling piece to obtain the distribution of the sediments in the etching chamber, so that the adjustment precision of etching process parameters is improved, and the device yield is improved; meanwhile, the representativeness of sediment distribution data is improved through the position distribution of the sampling bins; in addition, a sampling piece is placed in the sampling bin, so that the sampling piece effectively reflects the actual distribution condition of sediments on the side wall of the etching chamber, and meanwhile, operation and maintenance are convenient; finally, after the sampling piece is taken out, dry ice cleaning and radioactive substance detection are carried out in the etching chamber, and the influence of radioactive substance residues on the sediment distribution detection accuracy in the future and the damage to the etching chamber are avoided.

The invention provides a three-dimensional lithium battery mine visualization system based on digital twinning, and the system comprises a physical sensing layer which is disposed at a lithium battery mine site, and comprises a plurality of sensor networks used for collecting geologic bodies, production equipment, environment parameters, personnel positions, and vehicle states; and the data interaction layer comprises a data integration platform and an edge computing node, and is used for carrying out cleaning, fusion, protocol conversion and edge side preliminary analysis on the multi-source heterogeneous data uploaded by the physical sensing layer, and uploading the multi-source heterogeneous data to a cloud. By integrating the slope monitoring sensor and the professional analysis model, real-time evaluation and advanced early warning of the slope stability and the tailing pond safety are achieved, major accidents such as collapse and dam break are effectively prevented, meanwhile, the harmful element diffusion model is utilized, and the safety of the tailing pond is improved. Migration paths of fluoride dust, radioactive substances and potential leakage pollutants in the atmosphere and the water system are dynamically simulated, accurate decision support is provided for environmental risk emergency response, and the influence on surrounding ecology is reduced to the maximum extent.

An automatic doctor blade (1) for scraping a radioactive target (101) to be used for a radiopharmaceutical, the automatic doctor blade comprising: a target holder (2) for holding a radioactive target; a scraping unit (3) comprising a scraping member for scraping the radioactive target located in the target holder; a receiver (5) for receiving material scraped from the radioactive target; a motor (6) for moving the scraping unit and the target holder relative to each other; and a control unit for controlling the motor. A surface (102) of the radioactive target to be scraped is arranged at an angle between 45 degrees and 315 degrees, the angle of 0 degrees corresponding to the radioactive target being oriented such that the surface of the radioactive target to be scraped is perpendicular to the vertical direction and facing upward, the angle of the target corresponding to a clockwise rotation of the target from 0 degrees.

Disclosed is a system and a method enabling the behavior of a radioactive substance within a structure to be determined. More particularly, the disclosed is a system and a method wherein it is possible to determine, along a column, the position and / or distribution and / or movement speed of the substances moving within the column and / or the time when the substances will leave the column and how much of the substance reaching the column outlet will begin to leave the column and with what activity, and consequently, it is possible to provide optimization and automation for proceeding to the next process step.

The invention relates to the technical scheme. The invention belongs to the field of new energy and nuclear energy battery technology. The method is a comprehensive and systematic method for directly converting radioactive substances and radiation of the radioactive substances into electric energy. The utilization of radioactive substances is the utilization of a contact potential effect existing among substances with different Fermi levels. The utilization of the radiation is the utilization of the contact potential effect of a non-Fermi level; according to the technical scheme, the contact potential effect formed by the electric potential generated by radiation rays and radiation on a polar plate is utilized, and the effect is converted into electric energy capable of being actually utilized under the action of a medium which has conductivity and controls voltage and limits conductivity under a certain condition.

The invention belongs to the technical field of radioactive substance treatment, and discloses an HIC loading and dewatering device and a nuclear waste treatment method.In the HIC loading and dewatering device, a CASK secondary top cover grabbing assembly can be controlled to move through a first moving assembly and a first lifting assembly connected with the CASK secondary top cover grabbing assembly, and a secondary top cover of a CASK is grabbed through the CASK secondary top cover grabbing assembly; according to the technical scheme, the HIC top cover grabbing assembly can be controlled to move through the first moving assembly and the first lifting assembly connected with the HIC top cover grabbing assembly, the HIC top cover grabbing assembly is used for grabbing the HIC top cover, in addition, the dewatering head can be controlled to move through the second moving assembly and the second lifting assembly, and therefore the dewatering efficiency is improved. Therefore, the secondary top cover, the adapter, the HIC top cover and the dewatering head of the CASK can be assembled and disassembled without manual operation, and personnel can be prevented from being exposed for a long time.

Systems and methods use inserted dividers with control rod drives (CRDs) to flush CRDs from inside a reactor. Dividers separate flush zones from the reactor. Pumps, injectors, gravity, or any other drive, potentially in combination with draining pumps, vacuums, or other suctioning device, flow the fluid through the divider into the zone and back out of the same for flushing out radiation and debris or bringing about any other desired condition. A handling pole may extend several meters to allow operators to reach any CRD and place the divider and flushing components about the same. Flow paths may extend with the pole to deliver and remove the flush fluid to divider ports. Additional cameras, locators, detectors, batteries, etc. may be used to inspect and clean. The systems may clean CRDs whenever accessible, such as after a control blade or rod has been removed during a maintenance outage.

The present invention provides a method for three-dimensional positioning of radioactive materials indoors, comprising: step S1, establishing a UWB positioning system; step S2, establishing a Cartesian coordinate system for the indoor environment; step S3, obtaining positioning information of a nuclear detector and the count rate at that location; step S4, collecting the count rates of two adjacent fixed-angle detectors A and B at the same horizontal location; step S5, collecting the count rates of two adjacent fixed-angle detectors A and C at the same vertical location; step S6, inverting to obtain α; step S7, inverting to obtain α1; step S9, measuring the distance between the detector and the radioactive material; and step S10, calculating the coordinates of the radioactive material. The present invention also provides a three-dimensional positioning system for radioactive materials indoors.

Gamma camera imaging techniques, which include: Select (S101) from energy spectra recorded by a gamma camera on one or more radioactive materials, one or more energy ranges of each radioactive material, as one or more monitored energy ranges of the radioactive material; Performing (S102) an image reconstruction on the monitored energy ranges of each radioactive material among the one or more radioactive materials; Performing (S103) a normalization of the images obtained by image reconstruction; and Performing (S104) a superposition on the normalized images to produce a composite image, characterized by the fact that the selection includes: Sweeping through the energy spectra to find peaks and comparing the peaks with energies of branches of respective radioactive materials recorded in a predetermined nuclide bank to determine the one or more radioactive materials; Determine, for each radioactive material among the one or more radioactive materials, a portion of branches of the radioactive material with a relatively higher branch ratio or lower energy than one or more branches of the radioactive material to be monitored; and Determine, for each branch of the one or more branches, an energy range of the radioactive material centered on a central energy of the branch and having a width of half a height width of a peak corresponding to the branch as one of the one or more monitored energy ranges of the radioactive material.

A system and method for the measurement of radiation emitted from the body, for example, is presented. In one example, radiation sensors (e.g., gamma radiation sensors) may be used to measure activity proximate an injection site as a function of time. In some embodiments, one or more rangefinders may be employed to determine a size and / or position of a subject relative to the radiation sensors to better account for varying material densities within the system in estimating, for example, the amount of radioactive material in the tissue proximate the injection site. With an estimated function of radioactive material proximate the injection site as a function of time known, an estimated arterial input function may be determined, allowing for calculation of a correction factor that may be applied by a clinician during nuclear medical imaging. The magnitude, location, and volume of the radioactive source in the body may also be estimated.

The application discloses a kind of target detection method and system carrying radioactive substance.The method of the present application comprises: collecting the visible light image and radioactive image of the target to be measured;Based on the predetermined characteristics of each target to be measured are extracted based on the visible light image;Determine the first trajectory of the target to be measured based on multiple frames of visible light image within a predetermined time, and then assign a first weight w1 to each target to be measured based on the confidence sum value;Determine the second trajectory of radioactive material based on the radioactive image, and determine the second weight w2 of each target to be measured according to the matching similarity of the two trajectories;Determine the target to be measured with radioactive material based on the combination of the two weights.The method of the present application can detect suspicious target personnel carrying radioactive material at a relatively low activity, improve the correctness of radioactive material positioning screening in public places such as security check and customs, significantly reduce the false detection rate, and does not need to increase new hardware, stable and reliable.

A pierceable plug for closing off a piercing end of a needle is described herein. The plug has an end that is configured to be pierced by the needle to close off the piercing end of the needle. The plug may be radiation sterilizable and may be made of a material that includes an antimicrobial agent. The plug may be used to close off a needle end that is in fluid communication with a radioactive substance.

The invention discloses radioactive gas separation and purification equipment, a radioactive gas separation and purification method, a radioactive gas separation and purification medium and radioactive gas separation and purification equipment, and relates to the technical field of radioactive gas separation and purification. The radioactive gas separation and purification equipment comprises a first separation column, a second separation column, a carrier gas container, a quantitative structure, a chromatographic column, a detection assembly, a first control valve, a storage container, a temperature controller and a to-be-treated gas container. The carrier gas container is connected with the first control valve, and the to-be-treated gas container, the quantitative structure, the first control valve, the first separation column, the second separation column, the chromatographic column and the storage container are sequentially connected. The first separation column, the second separation column and the chromatographic column are all filled with stationary phases which are all used for purifying target substances in the to-be-treated gas based on different adsorption rates of the stationary phases relative to different substances. Therefore, due to the arrangement of the first separation column, the second separation column and other structures, large-volume ambient air or gaseous effluent can be purified, and subsequent radioactive substance concentration measurement is facilitated.

To provide a container (1) for transporting and / or storing a radioactive material (3), which comprises a cavity (12) for storing the radioactive material, and a radioactive protection device (14) composed of a radioactive protection element (16) arranged in an annular space (18).SOLUTION: According to the present invention, in relation to at least two contiguous radiation protection elements (16) from a longitudinal direction (8) and a circumferential direction (28) along a predetermined direction of an annular space, provided is a locking member (32) designed to limit / prevent the relative distance of the two radiation protection elements (16) in a predetermined direction.SELECTED DRAWING: Figure 8

To provide a radioactive material monitoring device capable of accurately detecting the concentration of radioactive materials in a liquid to be detected. [Solution] A radioactive material monitoring device comprising a flow channel through which a liquid to be detected flows, a counter unit that counts signals based on radiation generated from within the flow channel, and an analysis unit that calculates the concentration of radioactive material in the liquid to be detected based on the radiation count rate obtained from the counter unit, wherein the analysis unit includes a background correction unit that calculates a background value from the count rate based on the volume of the liquid to be detected in the flow channel and the count rate obtained from the counter unit, and a concentration calculation unit that calculates the concentration of radioactive material in the liquid to be detected based on the background value calculated by the background correction unit and the count rate obtained from the counter unit.

A method of forming a high internal phase emulsion (HIPE) foam is provided. A nitroxide-containing monomer can be used in combination with other monomers that can then be used to make a high internal phase emulsion foam upon curing. The nitroxide group can subsequently be used to control the radical polymerization of many monomers, which can be grafted from the surface of the high internal phase emulsion foam. The resulting foam can be useful in performing separations of radioactive species, metals, metal ions, multi-element ions, metal complexes, halides, and organic chemical species in chemical process streams, clean-up operations, etc.

The invention relates to the technical field of radiation protection, in particular to personal protection equipment for radiation detection, which comprises a helmet body, a support ring, connecting cloth and a protection component, and the protection component comprises an assembly groove, two standby grooves, a filter element, a magnetic annular unit, a lifting pushing unit and a transverse pushing mechanism. The lifting pushing unit drives the filter element needing to be replaced to move downwards, the filter element is pushed into the magnetic attraction annular unit through the transverse pushing mechanism and driven to the outside of the assembling groove through the magnetic attraction annular unit to be cleaned, and meanwhile the unused filter element is pushed out of the standby groove to be used in a linkage mode. After the external filter element is cleaned, the filter element is put into the assembly groove again for use; therefore, the working efficiency of ionizing radiation monitoring is remarkably improved, meanwhile, radioactive cross contamination of working places or workers caused by the fact that the workers need to enter and exit a high-activity area, a low-activity area, a clean area and other related areas of a non-sealed radioactive substance working place when the filter element is replaced is avoided, and therefore the physical health and life safety of the radiation workers are ensured.

To provide an electron-generating material and electron-generating member, which can reduce a friction coefficient.SOLUTION: An electron-generating material capable of reducing a friction coefficient is provided, the material comprising powder of a natural mineral containing a radioactive substance and powder of an electron-generating material that generates electrons when subjected to alpha rays emitted from the natural mineral, where the powder of the electron-generating material comprises titanium dioxide powder, lanthanum hexaboride, and silicon metal.SELECTED DRAWING: None