147 results about "Radioactive agent" patented technology

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.

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 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 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.

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.

Provided herein are compounds for delivery of one or more radiotherapeutic or radiodiagnostic agents. In some embodiments, the compounds have a radioactive agent binding moiety (RBM) connected to a GRPR binding moiety (GBM) through a linker (RBM-L-GBM), wherein the at least one of L and GBM is optionally substituted with an albumin binding moiety (ABM). In some embodiments, the one or more therapeutic or diagnostic agents are delivered to cancer cells.

A kind of quick bag sealing device and method for narrow space radioactive atmosphere isolation, including quick detachable inspection area, equipment back loading area, disassembly operation area;Wherein quick detachable inspection area, equipment back loading area, disassembly operation area all have sealing;And the top of quick detachable inspection area, equipment back loading area is equipped with crane hook reserved interface;Disassembly operation area side has PE operation glove, bottom has operation hole reserved interface.This application can significantly reduce the risk of radioactive material leakage by effective sealing mechanism, protect the operating personnel from radiation damage, while preventing radioactive aerosol from polluting the external environment.Using multiple sealing technology, including buckle and heat sealing, ensures zero leakage of radioactive atmosphere, meets strict radiation protection standards.Effective sealing and isolation measures reduce the possibility of radioactive material release into the environment, help maintain ecological safety.

The invention relates to the technical field of nuclear power station equipment, and discloses a flexible sealing feed-through line and rapid installation device for a nuclear power station, which comprises an outer shell, an end cover is installed in the outer shell, a cylinder is installed in the end cover, a cone is installed at the left end of the cylinder, and a spring is installed on the right side surface of the cone. A ball groove is formed in the outer side face of the cone, and a ball is installed in the ball groove. According to the invention, by arranging the flexible sealing pipe, the flexible adaptability and the sealing reliability are achieved, equipment installation deviation and vibration and thermal expansion and cold contraction in a nuclear power environment can be flexibly adapted, meanwhile, a first protective barrier is formed, leakage of radioactive substances and invasion of water vapor and external impurities are effectively blocked, and the sealing performance is guaranteed; the insulating layer can reliably isolate the conductor from an external structure, avoid electric leakage and short circuit risks, avoid equipment faults or potential safety hazards caused by insulation failure, and can resist loss of harsh working conditions such as temperature fluctuation and chemical medium erosion.

Methods and systems are provided for calibrating a single photon emission computed tomography (SPECT) imaging system. In one example, a collimated line source for calibrating a SPECT system comprises a radioactive material aligned along a central axis of the collimated line source and a plurality of collimator plates arranged perpendicularly around the central axis, the collimator plates including a material that substantially absorbs photons striking the collimator plates. The collimator plates may absorb photons emitted by the radioactive material in non-perpendicular directions, which are not used for calibrating the SPECT imaging system, thereby reducing an amount of radiation released in an environment of the SPECT imaging system during calibration. Due to the reduced amount of radiation to which people in the environment are exposed, short time increments between patient examinations may be advantageously used to collect calibration data, reducing an overall amount of time used for calibration.

The utility model relates to the technical field of nuclear emergency rescue, and discloses a body surface radioactive decontamination shelter device, which comprises a shelter body, an outer shelter door and a fresh air module, the shelter body comprises a cabin, the cabin comprises a changing room, a leaching room, a body drying room and a reinspection room which are communicated in sequence, the outer shelter door is movably arranged on the shelter body, and the fresh air module is arranged on the outer shelter door. The outer cabin door is used for closing or opening the cabin body, the fresh air module is arranged on the cabin body, an air inlet of the fresh air module communicates with the outside, and an air outlet of the fresh air module is formed in the reinspection room. According to the body surface radioactive decontamination shelter equipment, the body surface of a radioactive contaminated person can be decontaminated, and radioactive damage to the person caused by radioactive substances in the air in the decontamination process can be avoided.

To provide a radioactive substance removal device capable of enhancing efficiency of moisture removal as pretreatment of radioactive gas.SOLUTION: And a radioactive substance remover 3 that removes a radioactive substance from the gas from which moisture has been removed by the moisture remover 2, in which the moisture remover 2 has a flow path through which the gas flows, and removes moisture by cooling the gas in the flow path to frost moisture on a predetermined portion, and the flow path has a narrower flow path cross-sectional area or a shorter cooling wall surface distance on a downstream side than on an upstream side.SELECTED DRAWING: Figure 1

The invention provides a system and a method for realizing mitochondrial protein localization analysis through base editing and sequencing, which are a simplified platform without radioactive substances and are used for reporting the input and localization conditions of proteins to a mitochondrial matrix. The system and method of the invention can convert a mitochondrial input event into C-to-U base editing of a specific site in a mitochondrial genome. Subsequently, these edits are quantitatively analyzed by sequencing, enabling sensitive and scalable analysis of mitochondrial protein input under various genetic and chemical conditions. Different from a traditional input detection method, the system and the method provided by the invention integrate sensitivity, specificity and high throughput, and provide a multifunctional framework for analyzing subcellular protein localization change under genetic or chemical disturbance.

This utility model discloses a material container transfer device, including a support mechanism, a container gripper mechanism, a telescopic mechanism, a lifting mechanism, a rotating platform mechanism, a bottle flipping mechanism, and a bottle scanning mechanism. The container gripper mechanism is used to hold the container and is mounted on the telescopic mechanism, which drives the container gripper mechanism to extend and retract. The lifting mechanism drives the telescopic mechanism to move up and down together with the container gripper mechanism. The rotating platform mechanism is mounted on the support mechanism, as are the bottle flipping mechanism and the bottle scanning mechanism. This utility model implements a one-item-one-code-one-information system, enabling precise and efficient transfer of different material containers between various devices. It reduces manual intervention in the work area, lowers the probability of personnel misreading material information, misplacement, and exposure to radioactive materials due to containers falling off during transfer.

The present application relates to the technical field of product quality and safety, in particular to a high-throughput rapid screening method for radioactive substances in waste textile raw materials, comprising the following steps: step one, raw material preselection; step two, raw material pretreatment; step three, radioactive substance detection; step four, radioactive substance measurement and analysis; step five, detection of Sr-90 content in raw materials; and step six, reagent addition. The present application proposes a research on common gamma nuclides and Sr-90 content analysis in textile raw materials, ensures the radioactivity safety of textile raw materials, establishes a method for detecting radioactive substance Sr-90 in waste textile raw material solid waste by using a low-background alpha beta measuring instrument, the average recovery rate of the method is 80%, the average detection limit, and the radioactive detection of waste textile raw materials is studied. The research results show that the content of gamma radioactive nuclides in the selected waste textile raw material samples meets the national limit standard requirements, and reduces the pollution of common radioactive nuclides.

The utility model discloses a multifunctional radioactive substance classified storage device, and relates to the field of pollution disposal devices. A multifunctional radioactive substance classified storage device is characterized in that a plurality of storage assemblies are slidably connected in a box body, and a fetching drawer is slidably connected to the bottom of the box body; an overturning cover plate is rotationally connected in the box body, and a torsional spring is connected between the overturning cover plate and the box body; a back door is arranged on the box body, and a falling channel is formed between the overturning cover plate and the back door; the storage assembly comprises a connecting rod, a bottom plate, a back plate and a storage baffle, the back plate is connected with the storage baffle through the connecting rod, rollers are rotatably connected to the back plate, a supporting sliding rod is fixedly connected to the storage baffle, the supporting sliding rod is slidably connected with the bottom plate, a sliding rail is fixedly connected to the box body, and the connecting rod is slidably connected with the sliding rail; according to the utility model, other articles and the storage grids can be prevented from being radiated when a user takes out the articles in the box body in a radiation place, so that the box body does not need to be subjected to all-around decontamination treatment after being used every time.

The invention belongs to the field of Po-210 aerosol characteristic calculation, and particularly relates to a Po-210 aerosol particle characteristic and decay kinetics calculation method. The method comprises the following steps: S1, determining an optimal theoretical method; s2, constructing an initial molecular structure of one or more candidate Po species to be researched, and completing construction of the initial molecular structure; s3, geometric structure optimization and frequency calculation are carried out; s4, a Lennard-JonesLJ potential parameter is calculated, and the Lennard-JonesLJ potential parameter is calculated; s5, determining thermodynamic properties of the candidate chemical species based on the LJ potential parameters obtained in the step 4; and S6, calculating to obtain the characteristics of the Po-210 aerosol. Based on quantum chemistry, molecular dynamics and a Monte Carlo method, particle nucleation, collision and combination mechanisms and decay dynamics of Po-210 in a gas space are disclosed, key mechanism support is provided for predicting environment evolution behaviors and designing source foot control strategies, and a feasible calculation normal form is provided for predicting cross-scale behaviors of highly toxic radioactive substances.

A radiotracer injection system for safe use in industrial plants allows for rapid coupling of the radiotracer element storage bottle. The entire set is fully pneumatically driven and allows radiotracer injection in the form of a rapid pulse or step pulse. The injector system can be used with radiotracers in liquid (aqueous or oil) and gaseous form. The system is a sealed and safe unit to work in systems with internal pressure up to 300 Bar. This prevents the need to handle radioactive material in industrial plants, as the radiotracer used in each injection is already delivered inside its respective bottle. Quick-coupling connections allow quick and safe exchange of a used bottle for one with a new radiotracer, without having to disconnect the injector from the system. The injection machine has cylindrical symmetry, which allows the use of shielding with prismatic lead bricks, forming a protective castle around the unit.

The invention relates to the technical field of security check, and discloses an integrated system based on radioactive substance detection and X-ray radiation imaging. The system comprises an initial modeling module, a detection planning module, a signal acquisition module, a data fusion module, a collaborative analysis module and a comprehensive judgment module. The initial modeling module establishes a synchronous initial space model, the detection planning module generates a key detection subspace according to historical attenuation probability distribution of radioactive substances, the signal acquisition module captures radioactive signals and extracts an X-ray density image, and the data fusion module aligns two types of data time sequences and peels off independent signal streams. The collaborative analysis module identifies suspected core points and calculates X-ray absorption coefficient abnormal fluctuation, and the comprehensive judgment module obtains a judgment result. The system can improve the radioactive signal capturing efficiency, avoid signal interference and enhance the accuracy of radioactive substance judgment, and is suitable for the field of radioactive substance detection.

The invention relates to the technical field of sewage treatment and biological energy, and particularly discloses a method for converting sewage into biofuel for power generation. According to the method, a multi-factor synergistic system containing an inducing factor, a phagocytosis factor and a powdered sugar factor is generated through photosynthetic induction, the inducing factor destroys harmful microorganisms, the phagocytosis factor fixes radioactive substances, germs and viruses, and the powdered sugar factor serves as a carbon value locking precursor; organic pollutants are directionally converted into alcohol clean energy carriers by utilizing a multi-factor synergistic system, and meanwhile, fixed capture of the pollutants is completed; the carbon value is locked by a carbon value locking agent to generate a fixed carbon mixture, and the fixed carbon mixture is dehydrated and dried to obtain the high-purity biochar fuel. Unification of harmless treatment and energy utilization of the radioactive sewage is realized, and the limitation that the radioactive sewage cannot be treated in the traditional technology is broken through.

The embodiment of the invention relates to the field of metal remelting, in particular to a method suitable for manufacturing radioactive materials into molten ingots in a glove box, the method is carried out through a preset device, the device comprises a melting assembly, a vacuumizing assembly, an ingot forming assembly and a conveying assembly, and the method comprises the following steps that S10, the radioactive materials are put into the melting assembly; s20, a vacuumizing assembly is started, and the melting assembly is vacuumized; s30, the melting assembly is heated, so that the radioactive materials in the melting assembly are converted into a molten state; s40, the radioactive materials in the molten state are poured into the ingot forming assembly; s50, the ingot forming assembly is cooled, so that the radioactive materials in the molten state are formed into ingots; and S60, the radioactive materials obtained in the step S50 are subjected to ingot forming and removed out of the glove box through a conveying assembly. Through casting in the glove box, radioactive substances can be prevented from being exposed in an operation environment, and the safety of operators is ensured.

Provided is a radiation decomposition device and a radiation decomposition method that allow efficient decomposition of an irradiated substance while reducing the size of equipment as much as possible. A radiation decomposition device (100) according to the present invention is characterized by including: a radiation source (101) that emits radiation released from a sealed radioactive substance; a reaction tank (103) that contains a to-be-irradiated substance (104); and a heat transfer tank (102) that covers the radiation source (101) and transfers, to the reaction tank (103), heat generated by the decay of the radioactive substance. It is preferable that the radiation source (101) is: a radiation source formed of spent nuclear fuel or vitrified waste containing fission products extracted from spent nuclear fuel; a radiation source containing fission products extracted from spent nuclear fuel; a radiation source containing Co-60; a radiation source containing Cs-137; or a high-level radioactive waste liquid.

1. Name of the product in this design: Handheld radionuclide identifier. 2. Application of this design: This design is used for the detection of radioactive materials, dose rate measurement, and identification of radionuclides. 3. The key design feature of this product is its shape. 4. The image or photograph that best illustrates the design's key points: a 3D model. 5. The bottom surface of this product is a part that is not easily seen or cannot be seen during use, so the bottom view is omitted.