202 results about "Radiogenic nuclide" patented technology

The invention relates to the technical field of radionuclide separation, in particular to an Eu (III) / An (III) separation method based on a zirconium phosphonate-based metal organic framework adsorbent, which comprises the following steps: adding the zirconium phosphonate-based metal organic framework adsorbent into an Eu (III) and / or An (III) nuclide-containing aqueous solution with the acid concentration of 0.001-3M to carry out adsorption reaction, and then carrying out solid-liquid separation, wherein the zirconium phosphonate-based metal organic framework adsorbent is a zirconium phosphonate-based metal organic framework material exchanged by metal cations M; the metal cation M is selected from one of alkali metal ions, alkaline earth metal ions or divalent transition metal ions. According to the invention, the interlayer chemical properties of the material are regulated and controlled through ion exchange, so that the adsorbent has ultrahigh selectivity, rapid adsorption kinetics, high adsorption capacity and excellent structural stability on trivalent actinide / simulated nuclides in extremely high-acid, high-salt and intense-radiation environments; the key problems of low separation efficiency and poor stability in a high-acid complex system in the prior art are solved, and the method is suitable for treating high-level liquid waste.

The application provides a radionuclide nanohydrogel microneedle and a preparation method and application thereof, and belongs to the field of nanobiomedicine. 32 P-labeled calcium phosphate, which is formed by a biomimetic reaction of Ag2S@Ca 32 P nanoparticles, and a base layer which is a base matrix and comprises hyaluronic acid 32 P nanohydrogel microneedle can release Ag2S nanoparticles in response to a weakly acidic tumor environment, and under the irradiation of near-infrared light, the photothermal conversion efficiency can effectively kill bacteria, effectively improve the tumor hypoxic environment, enhance the treatment effect of radionuclides, play an antibacterial and wound healing promoting role in melanoma defect repair, and maximize the inhibition of tumor growth and tumor recurrence.

A dual-radionuclide production target includes a first radionuclide target that produces a first radionuclide when irradiated by a particle beam from a radionuclide production system, and a second radionuclide target that produces a second radionuclide when irradiated by the particle beam that has passed through, and been degraded by, the first radionuclide target. With this design, the first radionuclide target serves two purposes: it reduces the beam energy to a suitable energy for isotope production on the second radionuclide target, and in-doing so becomes activated with a medically relevant radionuclide that can be easily extracted. In this way, in a single production run can produce two or more radionuclides.

Methods for processing metal components from the nuclear industry are described. In some embodiments, a method includes processing a component having a surface contaminated with radionuclides by dissolving at least a portion of the surface with an acid solution to produce a waste solution including the radionuclides, and separating the radionuclides from the waste solution. In some embodiments, a method includes processing a component including a target radionuclide by immersing at least a portion of the component in an electrolyte bath, applying an electric current to cause electrodissolution, and electroplating the target radionuclide from the solution onto a cathode. In some embodiments, a method includes processing a metal composite component by dissolving it to produce a solution including dissolved metal and particulate material, and separating the particulate material.

1. The name of the design product: radiation measuring device. 2. The use of the design product: the design product is used for monitoring the radiation dose field of the environment radiation and analyzing the radionuclide deposition characteristics. 3. The design points of the design product: in shape. 4. The picture or photo that best indicates the design points: design 1 perspective view. 5. Design 1 is designated as the basic design.

This invention relates to the field of neutron source technology, and particularly to a controllable isotope neutron source device based on ion migration and a method for generating neutrons. The device includes a casing, inside which are a target material module, a target ion migration system, a safety module, and an alpha particle source term. The target material module provides target nuclide ions. The alpha particle source term includes alpha radioactive nuclide material and target nuclide intercalation material. The safety module is composed of target nuclide intercalation material. The target ion migration system is connected to an external control field. Target nuclide ions migrate through the target ion migration system within the safety module and the alpha particle source term. This invention enables active controllability of the isotope neutron source, significantly improving safety. By ensuring sufficient contact between alpha particles and target nuclides to form a molecular intercalation structure, the (α,n) reaction efficiency is greatly improved. Furthermore, this neutron source can be used in combination with multiple modules according to application requirements, effectively increasing the neutron output flux.

The present application relates to a kind of ice fresh water product in the defrosting device in the determination of gamma radionuclide, solve the problem that ice fresh water product in the determination of gamma radionuclide, the surface of sample box with ice fresh sample is condensed water and frost problem.The circumferential outside of the sample box of the device is provided with water receiving groove;The upper surface of the upper cover of the sample box is provided with transmission top plate, the bottom surface of the sample box is provided with transmission bottom plate, the upper surface of the transmission top plate is provided with driving roller in the middle, the left and right sides of the transmission top plate are provided with upper deflection roller, the left and right sides of the bottom end of transmission bottom plate or sample box are provided with lower deflection roller, water-absorbing cloth is sequentially wound around driving roller, left upper deflection roller, left lower deflection roller, right lower deflection roller, right upper deflection roller and connected to driving roller again.The sample box of frozen water product gamma radionuclide determination can be defrosted on surface, avoid sample box outer wall to form condensed water and frost, cause influence to the internal environment of detector.

The invention discloses a coated yttria-90 loaded radioactive microsphere and a preparation method and application thereof, and relates to the technical field of radioactive microsphere preparation, and the preparation method comprises the following steps: preparing a polyvinyl alcohol microsphere by using a microfluidic technology; the preparation method comprises the following steps: labeling polyvinyl alcohol microspheres with yttrium-90 radionuclide to obtain yttrium-90 loaded radiation microspheres; and coating the polylactic acid-glycolic acid copolymer on the surface of the yttria-90 loaded radioactive microsphere to obtain the coated yttria-90 loaded radioactive microsphere. The composite radioactive microspheres with uniform particle size, stable radioactivity and controllable characteristics can be obtained, and the composite radioactive microspheres are expected to be applied to transcatheter arterial radioembolism (TARE) treatment of liver cancer.

The invention relates to a method for separating heavy metal cations and radionuclides from aqueous solutions. The method according to the invention can be used to separate dissolved and / or suspended naturally occurring ions or radioactive ions produced by radioactive decay, nuclear transformation reactions such as nuclear fission, or, for example, by activation with neutron radiation, from aqueous solutions.

The invention relates to the technical field of radionuclide data analysis, in particular to a half-life period parameter generation method and device, equipment and a storage medium. Analyzing the sampling data set based on a random forest regression model to obtain a first half-life period correction coefficient; analyzing the sampling data set based on a multiple linear regression method, a preset humidity correction function and a preset storage time length correction function to obtain a second half-life period correction coefficient; according to a preset dynamic coupling relation updating model, the first half-life period correction coefficient and the second half-life period correction coefficient, generating a real-time half-life period parameter; by integrating multi-source heterogeneous data support model training, real-time half-life parameters are generated, a reliable tool is provided for food safety supervision and the like, industry development is assisted, and economic and social values are achieved.

This invention discloses a method for estimating radioactive release during the preparation of radioactive metal waste, comprising the following steps: (1) conducting gamma dose rate surveys and delineating the distribution of radioactive pollution in the radioactive source area; (2) setting up monitoring points in the radioactive metal waste areas with different pollution levels, and calculating the radioactive residue in the metal waste based on the monitoring data; (3) calculating the total release of each nuclide in the metal waste based on the above-mentioned radioactive residue in the metal waste and the obtained concentration data of radionuclides in the metal waste. By conducting gamma dose rate surveys and delineating the distribution of radioactive pollution in the radioactive source area; setting up monitoring points in the delineated areas to obtain the radioactive residue in the metal waste; and calculating the total release of each nuclide using formulas, the process is simple, easy to operate, and can obtain effective data on the total release of nuclides, providing data support for the preparation of radioactive contaminated metal waste and supporting the assessment of the dose caused by contaminated metal waste to the public.

The application relates to the technical field of quartz crystal purification, and particularly discloses a method for eliminating radioactive elements in quartz crystals, which comprises the following steps: adding quartz sand into a composite cleaning solution, stirring and cleaning, then performing solid-liquid separation and water washing to obtain pretreated quartz sand; performing heat treatment on the pretreated quartz sand in an oxygen-containing atmosphere at 850-1000 DEG C for 2-4 hours to obtain heat-treated quartz sand; rapidly cooling the heat-treated quartz sand in cooling water at 10-30 DEG C for 15-30 seconds, then crushing and screening to obtain crushed quartz sand; adding the crushed quartz sand into a selective acid cleaning solution under stirring to perform an acid cleaning reaction, then performing solid-liquid separation, washing and drying after the reaction to obtain low-radioactivity quartz sand. The composite cleaning solution and the selective acid cleaning solution are used in cooperation to efficiently remove radioactive elements such as uranium and thorium in the quartz crystals, and the physical and chemical properties of the quartz crystals can meet the requirements of high-end semiconductor and optical applications.

The application provides a pulse neutron element scanning and analyzing system for extraterrestrial exploration, which comprises a shell, a support, a neutron generator, a shielding body and a gamma spectrometer, the support is installed in the shell, the neutron generator, the shielding body and the gamma spectrometer are all installed on the support, and the shielding body is located between the neutron generator and the gamma spectrometer. The neutron generator, the shielding body and the gamma spectrometer are integrally installed on the support, the controllable neutron source is combined with the gamma spectrometer, the stratum is activated by the controllable pulse neutron generator, the element components are detected by gamma analysis, or the gamma generated by the natural radioactive nuclides and the cosmic background radiation is directly detected, element component analysis is carried out, the element measurement precision is improved, the detection time is shortened, more kinds of elements can be measured, and the application provides strong support for the measurement of more kinds of elements, and is suitable for lunar geology and resource exploration.

The present invention provides a radioactive nuclide separation device and a fluid recovery method using the same. [Solution] The radionuclide separation apparatus according to the present invention is an apparatus for separating a desired radionuclide, and may include: a fluid supply unit for supplying a fluid containing a sample or reagent containing a radionuclide; a column separation unit including a drive member flow path for receiving the fluid supplied from the fluid supply unit, separating the radionuclide, and discharging the fluid from which the radionuclide has been separated; a fluid recovery unit including a plurality of recovery containers for recovering the fluid that has passed through the column separation unit and been discharged; a sensor for sensing the fluid in the column separation unit; and a control unit that controls the driving of the fluid supply unit, the column separation unit and the fluid recovery unit so that after residual fluid remaining inside the drive member flow path is recovered into the recovery container, the recovery container located at the recovery position is changed.

Cobalt intermetallic compounds that include cobalt and a second element are provided. The isotopes of the second element in the compounds are present in their natural isotopic abundance or in an enriched isotopic abundance. Methods of making the compounds and methods of using the compounds as targets in the production of radionuclides are further provided.

The invention provides a water quality on-line analysis method and system in a radioactive waste liquid treatment process, and relates to the technical field of water quality on-line monitoring, and the method comprises the following steps: 1, introducing a clarified sample into an analysis pool, and collecting Raman spectrum characteristic peak data in real time through a plurality of groups of optical fiber Raman probe arrays arranged in the analysis pool along a waste liquid flowing direction; performing principal component analysis on the Raman spectrum characteristic peak data, extracting characteristic spectrum vectors corresponding to main radionuclides and interferents, and constructing a two-dimensional concentration distribution field according to continuous changes of the characteristic spectrum vectors in spatial positions; 2, isoconcentration lines are extracted from specific interferent components in the two-dimensional concentration distribution field, discrete sampling is carried out, the minimum circumcircle of all sampling points is calculated, and the circle center coordinates and the radius of the isoconcentration lines are obtained; the system realizes intelligent regulation and control of treatment process parameters, and ensures that the discharged water quality is stable and reaches the standard.

The invention relates to a cyclotron which enables the production of α- or β-emitting radionuclides. The cyclotron, with a magnetic periodicity of 3, comprises three accelerating cavities connected to the centre, thus not requiring phase control between the cavities, forming a single high-frequency resonator. The six accelerating gaps per turn enable rapid acceleration (the angle ϕ between the accelerating gaps of each cavity being approximately 30°) which is essential for acceleration at the third and sixth harmonics. This cyclotron preferably has an injection system (31) supplied by different types of ion sources, making it possible to efficiently accelerate charged particles having Z / A ratios equal to 1 / 2 and to 1 / 4. The cyclotron may also have stripping extraction means positioned in the cyclotron so as to extract the charged particles and double their state of charge. These particles enable a set of nuclear reactions for producing α-emitting radionuclides.

The invention relates to the field of nuclear power operation, in particular to a method and a device for recycling boron removal resin of a primary loop of a nuclear power plant. In the device, the anion exchange filter of the primary loop waste liquid distillation system is connected in parallel with the boron removal filter of the primary loop coolant treatment system. The method comprises the following steps: during normal operation, when the boric acid concentration of a primary loop is reduced to 0.3 g / L-0. 2g / L at the end of a fuel circulation life period, a boron removal filter is put into operation; in the overhaul period, an alkali removal filter and a boron removal filter are put into operation at the same time; and after the overhaul is finished, jointly commissioning a cation exchange filter and a boron removal filter of the primary loop waste liquid distillation system to purify the concentrated boric acid storage tank. The use efficiency of the boron removal filter is improved, the boron removal filter can be used for removing key radionuclide Sb-124 in each overhaul period, and meanwhile the use of new resin and the generation amount of radioactive solid waste are not increased.

1. Name of the product in this design: Radionuclide Energy Spectrometer Detector and Analyzer. 2. Purpose of this design: This design is used for the energy spectrum detection 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: 3D view 1.

In an embodiment of the present disclosure provided is a method of producing radionuclides that includes the installation, irradiation, transport, and trapping steps. In the installation step, a target material containing a target nuclide is placed inside a target chamber. In the irradiation step, at least a portion of the target material is irradiated with a quantum beam. In the transport stage, a carrier gas is supplied to the inside of the target chamber and an ambient gas around the target material is sent to the outside of the target chamber through an exhaust pipe. In the trapping step, a trap device connected to the exhaust pipe is configured to trap the radionuclides produced from the target nuclide from the ambient gas. In the present embodiment of the present disclosure, the target nuclide is bismuth 209 and the produced radionuclide is astatine 211. In an embodiment of the present disclosure, a target holding device 100 for quantum beam irradiation comprising a target material container 3 and a rotational drive mechanism 5 is also provided, as well as a quantum beam irradiation system 1000. An example target material container is rotatable.

The present disclosure provides a simple and versatile process suitable for large-scale production of alpha emitters. It does not require irradiation of the source material and it is based on aqueous solutions and a strong cation exchange resin.

The present application relates to the technical field of health-care materials, and discloses a rare earth composite energy health-care product based on synergy and a preparation method thereof, which comprises monazite fine powder 10 parts by weight, silico-aluminate composite network forming agent 75-80 parts by weight, in-situ reduction and network modifier 5-10 parts by weight, and pore forming agent 3-5 parts by weight; the preparation method comprises the following steps: crushing and grading the raw ore to obtain fine powder by intercepting high-density radioactive associated ore; mixing and kneading the fine powder and the remaining components to form a green body; performing three-stage step calcination to sequentially complete low-temperature pore forming, high-temperature magnesium hot reduction to generate lattice oxygen vacancies, and introduction of high-temperature water vapor to promote the generation of amorphous liquid phase to solid-solution-embed radioactive nuclides; and finally, forced air cooling and depolymerization and crushing are performed to obtain the finished product. The present application effectively reduces the radioactivity background of the material, blocks the physical channel for the escape of decay gas, and enables the product to have the functions of safe and stable far-infrared radiation and release of negative oxygen ions.

The invention discloses an entry sample gamma radionuclide passive efficiency calibration method and system, and the method comprises the steps: collecting entry sample nuclide distribution, detector response, measurement geometry and other basic parameters, and then calling a ray direct penetration rate prediction model to calculate penetration rate data, an optimized detector parameter set is generated through a detector parameter characterization optimization model, correlation mapping of energy spectrum data and efficiency scale parameters is completed through an entry nuclide energy spectrum data analysis platform, target nuclides are recognized through a nuclide type recognition matching algorithm, feature parameters are extracted, and finally passive efficiency scales are completed. According to the method, a collaborative linkage mechanism is formed by integrating multiple models, a systematized data processing link is established, scenes with complicated types of entry samples and non-uniform nuclide distribution are effectively adapted, the accuracy and consistency of scales can be guaranteed without depending on a standard source, and efficient and reliable technical support is provided for entry nuclide detection.

The invention relates to a high-radioactive waste disposal simulation method and system based on multi-field coupling. The method comprises the following steps: constructing a three-dimensional finite element model of a high-radioactive waste repository and a surrounding geological medium based on physical field simulation; simulating temperature change around the high-radioactive waste repository, underground water flow velocity change and radionuclide concentration change; based on a geochemical calculation model, performing chemical reaction calculation on the distribution of the radioactive concentration of the high-radioactive waste in underground water and rock-soil media, including dissolution, precipitation, adsorption and ion exchange of the high-radioactive waste; and carrying out iterative coupling on the physical field simulation and the geochemical calculation model, and outputting a high-radioactive waste disposal simulation result which comprises a radionuclide concentration three-dimensional distribution diagram, a migration flux vector diagram and temperature field distribution. Through iterative coupling of a physical field and a chemical field, high-precision simulation prediction of nuclide migration behaviors in a high-radioactive waste long-term disposal environment is realized, and a simulation result is close to an actual migration process.

This method for converting the radioactivity of each nuclide using an artificial neural network comprises the steps of: analyzing a spectrum of a radionuclide by using an artificial neural network and outputting an output layer of the artificial neural network as the radioactivity ratio of each nuclide; and converting the radioactivity ratio of each nuclide into the radioactivity of each nuclide.

The invention discloses a waste treatment method in a radiopharmaceutical production process, which comprises the following steps: adding a DNA-silver nano composite material into wastewater, so that silver ions are combined with iodine-131 to generate stable silver iodide crystals, thereby fixing radionuclides in the wastewater; the risk of iodine-131 volatilization is reduced by adopting a vacuum evaporation process, and water is ensured to be separated from radioactive pollutants; condensate water is discharged after reaching the standard through detection, and concentrated waste is subjected to curing treatment; by mixing concentrated waste with cement and adding a silicate additive, the physical stability and chemical inertness of a solidified body are enhanced, and the possibility of leakage is reduced; and finally, safely storing the cured concentrated waste in a special storage container. According to the method, efficient and safe radioactive waste management is achieved through the synergistic effect of a series of steps, the safety of long-term storage is greatly improved, and the method has great significance in protecting human health and protecting the ecological environment from radioactive contamination.

The invention provides a composite target material for producing astatine-211 through a cyclotron and an active cooling system of the composite target material, and relates to the technical field of radionuclide preparation. The composite target material comprises a working part and a connecting part which are integrally formed, the upper surface of the working part is provided with an inclined surface or a concave curved surface used for depositing a bismuth layer, and a plurality of liquid cooling runners communicated with one another are integrated in the connecting part; the active cooling system further comprises a supporting cooling base detachably connected with the composite target material, and the supporting cooling base and the composite target material jointly form a closed circulating cooling loop. The thermal load distribution can be optimized by changing the geometric configuration of the working surface, and the integrated liquid cooling and modular assembly and disassembly design is combined, so that efficient heat dissipation is realized, and meanwhile, rapid replacement of the target material is supported. According to the system, the anti-meltdown capability and the operation stability of the target material are remarkably improved, and the system is suitable for large-scale high-yield preparation of astatine-211.

The present application provides a suspension containing radioactive microspheres, a preparation method and application thereof. The radioactive microspheres include resin microspheres and a radionuclide loaded on the resin microspheres, the material of the resin microspheres includes at least one of polystyrene, polyethylene or polydivinylbenzene, or a crosslinked polymer thereof, the average particle size of the radioactive microspheres is 25-40 μm, and by controlling the non-spherical ratio of the radioactive microspheres within 5%, the distribution density of the microspheres in the tumor part is improved, the killing effect on the tumor is improved, and the incidence of adverse events is reduced.

The invention relates to the decontamination of radiation-contaminated lands with clay and loose soil, such as agricultural lands, as well as abandoned test sites, such as the Semipalatinsk test site and uranium quarries. In the method for decontaminating radioactively contaminated lands, which includes the introduction of a reagent, according to the invention, the area of ​​the land to be treated is filled with a 5-7 cm thick layer of KB3 grade barite concentrate containing at least 90% barium sulfate, or finely crushed barite-lead ore containing 70% barium sulfate and up to 1% lead sulfate, Then the land is ploughed using a heavy eight-body plow to a depth of at least 300 mm, turning over the soil layer and dumping it in an inverted position for the complete burial of the radioactively contaminated mass, after which the land is harrowed and reclaimed with the sowing of grass seeds. The developed method for decontaminating radioactively contaminated lands makes it possible to decontaminate lands over a large area and eliminates the need to extract fragments containing adsorbed radionuclides from the soil.

The invention belongs to the technical field of nuclear energy accident treatment, and relates to a high-temperature gas cooled reactor accident condition typical nuclide chemical form research method and system and a readable medium. Inputting the data into an accident source item calculation model to obtain the content change condition of each radionuclide and impurity element along with time; obtaining a chemical form evolution result along with temperature and a chemical form evolution result along with time through a thermodynamic method; determining a Latin hypercube sampling range, constructing an EMSAC input file, and running EMSAC calculation to obtain an element chemical form database in a multi-parameter variation range; and obtaining a correlation analysis result of the element chemical form database. The method solves the problems that in the prior art, accident source items cannot be processed, chemical forms evolve along with time and dimension explosion occurs during multi-parameter multi-change range calculation, accident source item whole-process calculation is completed for the first time, and theoretical reference is provided for subsequent radiation safety evaluation of nuclear facilities.