284 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 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 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 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 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.

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 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.

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.

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

A container for storing high assay low enriched uranium hexafluoride (UF6) has a cylindrical lateral wall extending between first and second heads defining a container interior for receiving the radioactive material. A plurality of cylindrical poison rods extend in parallel through the container interior. Each of the poison rods has a neutron absorber. A plurality of access nozzles are situated within the first head and / or second head. Each of the access nozzles has a lateral wall defining a throughway that extends through the first head between an interior end region and an exterior end region. The interior end region captures and supports a respective end of a respective poison rod. The exterior end region is opened and closed via respectively detaching and attaching an end cap to thereby respectively expose and contain the respective poison rod.

The utility model discloses a kind of C-14 samplers, it relates to radioactive material sampling equipment technical field, it includes sampling box and air inlet sampling head, catalytic converter and several sampling bottles are equipped in sampling box, sampling bottle is used to hold gas collection liquid in, bubbler is installed in sampling bottle;Sampling bottle includes side by side arranged first sampling bottle, second sampling bottle, third sampling bottle and fourth sampling bottle;The air inlet end of first sampling bottle is communicated air inlet sampling head, the air outlet end of first sampling bottle is communicated the air inlet end of second sampling bottle;The air outlet end of second sampling bottle is communicated the air inlet end of catalytic converter, the air outlet end of catalytic converter is communicated the air inlet end of third sampling bottle, the air outlet end of third sampling bottle is communicated the air inlet end of fourth sampling bottle, the air outlet end of fourth sampling bottle is communicated with power air pump. By this, the utility model is catalyzed by catalytic converter to gas catalytic conversion, improve the absorption effect of C-14, reduce error, improve the accuracy of detection result.

The utility model provides a gas purification system of a reactor. The gas purification system comprises a purification pipeline, and an inert gas adsorber, an iodine adsorber, a polonium processor, a filter and a radioactivity analyzer which are arranged on the purification pipeline. And the inert gas adsorber is used for removing inert gas in the mixed gas. The iodine adsorber is used for removing iodine in the mixed gas. The polonium processor is used for removing polonium in the mixed gas. And the filter is used for removing small particles in the mixed gas. And the radioactivity analyzer is used for detecting the radioactivity of the mixed gas. According to the gas purification system, aiming at the characteristics of radioactive substances of the metal fast reactor, a four-stage purification treatment device is arranged to remove radioactive gas in the mixed gas, and in addition, a radioactivity analyzer is further arranged and used for detecting and judging whether the radioactivity in the gas meets the emission standard or not; and the problem of radioactive substance release caused by leakage of the containment is effectively avoided.

The invention relates to the technical field of radiation measurement, in particular to a high-radioactivity volatile liquid on-line measuring device and method.The measuring device comprises an overflow pool, a lead shielding body and a detector, a detection channel is formed in the axis area of the lead shielding body in the vertical direction in a penetrating mode, and an orifice in the bottom of the detection channel is sealed through a window plate; a detector is coaxially arranged in the detection channel, and a light-sensitive surface of the detector directly faces the window plate; the lower end of the lead shielding body is embedded and fixed at the top opening of the overflow pool, so that the top of the overflow pool and the bottom of the lead shielding body define an annular airflow channel. The detector is arranged in the detection channel in the lead shielding body, and the dynamic air curtain isolation layer is constructed between the bottom of the lead shielding body and the liquid level of the overflow pool, so that the upward diffusion of volatile radioactive substances is physically blocked while gamma ray penetration measurement is realized, the detector and a light-sensitive surface are fundamentally prevented from being polluted, the maintenance frequency is remarkably reduced, and the measurement accuracy is improved. And the long-term measurement precision and the online continuous operation capability of the system are ensured.

The invention discloses a new energy power system which comprises a temperature difference driving module composed of a shape memory alloy element, and a clock transmission module mechanically connected to the temperature difference driving module. The environment adaptation module is integrated on the temperature difference driving module and / or the clock transmission module; the invention relates to the technical field of new energy power generation, the system utilizes the huge day and night temperature difference of the moon to generate power through the periodic deformation of a shape memory alloy element, and compared with traditional fossil fuel power generation, the system does not need to consume limited resources and is convenient to use. Greenhouse gases and pollutants are not generated, and the method is environment-friendly to the moon; compared with nuclear power generation, the risk of radioactive substance leakage does not exist, the safety control requirement is relatively low, and the construction and maintenance cost is lower.

A radiation monitoring system includes an optical fiber. The system further includes a scintillating fiber operatively coupled to a first end of the optical fiber at a first end of the scintillating fiber. The system also includes a damage detection device configured to detect damage to at least one of the optical fiber and the scintillating fiber.

The embodiment of the invention relates to the field of manufacturing of fixed-length products, in particular to a device and method suitable for preparing a metallographic sample of a radioactive material and the metallographic sample of the radioactive material. According to the device and the method, a radioactive material, a metal seat body and an outer sleeve are fixed into an integrated solid piece through resin, so that overall transfer positioning is facilitated, the exposure area of radioactive substances can be reduced in the cutting and polishing process, and the risk that operators make contact with radioactivity is reduced; the solid part can be effectively prevented from moving by cutting and grinding as a whole, and the stability and accuracy of the cutting and grinding process are ensured; the resin can buffer and disperse local stress applied to the radioactive material, the damage risk is reduced, and a thinner metallographic specimen can be prepared under the condition that the integrity of the radioactive material is kept. The thickness of the metallographic sample of the radioactive material provided by the embodiment of the invention can be accurately controlled at the target size, so that the microstructure on the surface of the sample can be clearly displayed, and the matrix interference is reduced.

The present disclosure provides a fusion system and method for radiation imaging and radioactive material monitoring of a baggage or package item. The fusion system includes a radiation imaging subsystem configured to operate in a pulsed mode to radiation image the baggage or package item, a radioactive material monitoring subsystem configured to operate in a pulsed mode to monitor whether the baggage or package item contains radioactive material, and a synchronization control subsystem in communication with both the radiation imaging subsystem and the radioactive material monitoring subsystem and configured to control the radiation imaging subsystem and the radioactive material monitoring subsystem to operate alternately.

The invention provides a fungus crust decontaminant for surface radioactive contamination removal and a preparation method and application thereof.The fungus crust decontaminant comprises konjac glucomannan, carboxymethyl cellulose, glycerol, a fungus microbial agent with fungus thalli being aspergillus niger A3 and distilled water, and all the components are natural or biodegradable substances; by optimizing the proportion, the detergent can effectively remove radioactive substances on the surface of an object through fungal crust and reduce the risk of radioactive contamination, the use method is simple and convenient, harmful conditions such as high temperature, high pressure or strong acid and strong alkali are not needed in the decontamination process, the environmental protection property and safety of the treatment process can be ensured, secondary pollution to the environment is avoided, and the environment-friendly effect is achieved. The method is suitable for treating various material surfaces, and has the advantages of high efficiency, environmental protection and safety.