340 results about "Radiogenic nuclide" patented technology

The invention discloses an ocean in-situ radioactivity monitoring method, which is characterized in that feature extraction is carried out based on a maximum likelihood expected value maximization (MLEM) algorithm, and spectrum unfolding operation is carried out by adopting a multi-layer perceptron. The method comprises the following steps: firstly, measuring FWHM related parameters of a CeBr3 detector by adopting a standard source, simulating the response of the detector to gamma rays in a marine environment based on a Monte Carlo method, and establishing a full-spectrum response matrix H in a range of 0-2048keV; based on the response matrix H, reconstructing a gamma energy spectrum y obtained by the detector by using an MLEM iterative algorithm; and the reconstructed spectrum is used as the input of a multi-layer perceptron (MLP), and qualitative and quantitative analysis of radionuclides in the energy spectrum is realized. According to the method, the discrete characteristic peak signal is convolved into the single path address corresponding to the characteristic energy, so that the accuracy of the MLP model in the spectrum unfolding process is effectively improved.

The invention discloses a nuclear accident emergency three-layer coupling network model and a construction method, and relates to the crossing field of nuclear accident emergency management and complex system risk simulation. The nuclear accident emergency three-layer coupling network model comprises an RMN layer which is used for simulating the dynamic diffusion process of radionuclides leaked by a nuclear accident in the atmosphere; the IN layer is used for constructing a spatial distribution and dependency relationship network of infrastructures; the EN layer is used for topologically defining a command or cooperation relationship of the emergency organization; according to the three-layer network coupling mechanism, when RDR of a middle grid is larger than or equal to RDRmax-1, IN-layer nodes in the middle grid at the same position are marked to be in a damaged state; and quantifying the bidirectional dependence density of the IN layer and the EN layer through the coupling strength epsilon. The method is used for predicting the direct risk of radioactive contamination in a nuclear accident and the secondary risk caused by emergency evacuation, revealing the risk evolution law, quantifying the risk diffusion scale, determining key influence factors, and providing a theoretical basis for formulating an emergency strategy.

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.

Systems and methods for generating radionuclides, such as radium-224, are disclosed herein. Systems herein may include a first cartridge having a first opening, a second opening, and a chamber therebetween having a first resin having affinity for thorium-228 and bismuth-212; a second cartridge having a first opening, a second opening, and a chamber therebetween having a second resin having affinity for thorium-228, a third cartridge having a first opening, a second opening, and a chamber therebetween comprising a third resin having affinity for thorium-228 and bismuth-212, and a fourth cartridge having a first opening, a second opening, and a chamber therebetween having a fourth resin having affinity for lead-212; wherein a continuous flow path is formed from a top of the first cartridge though the second cartridge, through the third cartridge, and to a bottom of the fourth cartridge during system use.

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.

Systems and methods for generating radionuclides, such as radium-224. Systems herein may include a first cartridge having a first opening, a second opening, and a chamber therebetween having a first resin having affinity for thorium-228 and bismuth-212; a second cartridge having a first opening, a second opening, and a chamber therebetween having a second resin having affinity for thorium-228 and bismuth-212, a third cartridge having a first opening, a second opening, and a chamber therebetween comprising a third resin having affinity for thorium-228 and bismuth-212, a fourth cartridge having a first opening, a second opening, and a chamber therebetween having a third resin having affinity for lead-212; wherein a continuous flow path is formed from a top of the first cartridge though the second cartridge, through the third cartridge, and to a bottom of the fourth cartridge during system use.

The invention discloses a comprehensive evaluation method for soil pollution in a decommissioned uranium mine area, relates to the technical field of environmental evaluation, and solves the technical problem that a soil pollution evaluation method is not clear due to lack of soil pollution data in an existing decommissioned uranium mine area. According to the technical scheme, the method is characterized in that the influence of radionuclides, environmental ecology, environment and biological effects in the decommissioned uranium mine area soil on the soil quality is comprehensively considered, key influence factors influencing the uranium mine area soil quality can be screened out, and the problems that existing data is lack, and a research method is not clear are solved; and a basis is provided for subsequent sustainable utilization of soil and environmental health.

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.

The invention discloses a method and equipment for identifying a radon release dominant channel in a granite surrounding rock underground space, a medium and a product, and relates to the field of data processing. The method comprises the following steps: according to content information of granite surrounding rock radionuclides, obtaining space distribution characteristics of radon parent nuclides in different types of surrounding rocks, and combining the characteristics to obtain radon background characteristics of an underground space; the method comprises the following steps: acquiring the distribution characteristics of faults, fractures or flowing water fractures at high radon concentration points in underground space air, and identifying the fracture occurrence information and radon precipitation dominant channel information corresponding to potential radon precipitation dominant channels by using the distribution characteristics; and based on radon precipitation dominant channel information and in combination with underground space ventilation conditions, screening to obtain radon measurement instrument point locations to be arranged by the radon continuous monitoring system. According to the invention, accurate identification of the radon release dominant channel is realized, technical support is provided for design of a radon continuous monitoring system in an underground space, and scientific support is provided for radon protection in the underground space.

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 discloses an electrochemical denucleation decommissioning facility oxide layer method based on a synergistic acidic electrolyte, and relates to the technical field of cleaning. The method comprises the following steps: by taking a polluted metal component as an anode and an inert electrode as a cathode, immersing the polluted metal component into a synergistic acidic electrolyte of a low-concentration acidic medium, and stripping an oxide layer on the surface of the polluted metal component until a clear grain boundary is exposed at the temperature of lower than 40 DEG C in a high-voltage direct-current electrolysis mode. By developing a synergistic enhanced acidic electrolyte system, high decontamination rate is realized in a low-concentration sulfuric acid medium, radionuclide stripping is accurately controlled to avoid matrix pitting corrosion damage, and high-valence nuclides in a compact oxide layer are deeply removed, so that the decontamination efficiency is improved. Finally, an efficient, low-damage and stable-process radioactive contamination metal treatment scheme is provided for nuclear facility decommissioning engineering. The method is suitable for removing radioactive contamination oxidation layers on the surfaces of the inner walls of stainless steel pipelines and reactor containers in nuclear facility decommissioning projects, and radionuclides are enriched in the oxidation layers.

The invention discloses a < 68 > Ge separation and purification method and an automatic system, belongs to the technical field of radionuclide separation, and aims to solve the problems of large amount of waste liquid, complex operation and difficulty in continuous production in the conventional < 68 > Ge separation method. According to the separation method in which the actinide resin column and the glucose gel resin column are connected in series, selective adsorption, impurity removal and desorption of < 68 > Ge are completed step by step by accurately controlling the acidity of the solution, an eluting agent and an eluent; finally, a set of continuous-automatic separation system is provided, the design that two sets of separation columns are connected in parallel is adopted, work-regeneration circulation alternation is achieved through program control, and full-automatic continuous production is achieved. The method has the beneficial effects that the 68Ge recovery rate is high, the product purity is high, the waste liquid amount is remarkably reduced, meanwhile, automatic operation and continuous production are realized, and a core technology and equipment support is provided for localization of 68Ge.

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 invention relates to a multi-permeable reactive barrier developed for use in nuclear power plants, which provides the uptake of cesium and strontium radionuclides, and contains at least one upper cover (1) providing fixation, through which the liquid enters; at least one lower cover (2) providing fixation, through which the liquid exists (drainage); at least one sealing element (3) positioned to separate each component from each other; at least one liquid permeable filter (4); and at least one body (5) containing zeolite, diatomite, clay and sepiolite components, respectively from top to bottom.

The present application discloses a radiation dose rate assessment method, device, storage medium and equipment in three-dimensional space, which belongs to the field of radiation detection technology. The concentration data and physical parameter data of the radioactive nuclide at least one first position point in the three-dimensional space are obtained; the three-dimensional convolution of the photon flux rate of the second position point is determined, and its final kernel function is the kernel function composed of the interpolation basis functions of the first position point and the second position point obtained by approximating the original kernel function according to the FMM; the concentration data and the physical parameter data are convoluted using the three-dimensional convolution to obtain the target photon flux rate; the radiation dose rate in the three-dimensional space is assessed based on the physical parameter data and the target photon flux rate. The present application can quickly calculate the radiation dose rate of continuous and arbitrary discrete positions, reducing the computational complexity and computational cost; it can assess the radiation dose rate of complex building scenes based on the shielding matrix, and accelerate the dose calculation and improve the calculation accuracy through the nested grid FMM.

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 invention relates to the technical field of nuclear reactors, and provides a high-temperature gas cooled reactor system. The system comprises: a reactor; the combined converter is connected to an inlet of the reactor; the burnup measuring device is connected to an outlet of the reactor; the sipping analysis device is connected between the burnup measuring device and the combined converter, a detection cavity is formed in the sipping analysis device, and the sipping analysis device is used for receiving the fuel balls from the burnup measuring device and can establish a negative pressure environment in the detection cavity so as to detect the activity value of target radionuclide in the gas in the detection cavity; the control module is electrically connected with the combined converter, the burn-up measuring device and the sipping analysis device; when the burnup value is smaller than a set burnup threshold value and the activity value is smaller than an activity constraint value, the control module controls the combined converter to return the fuel balls to the reactor for recycling; when the burnup value is larger than or equal to a set burnup threshold value or the activity value is larger than or equal to an activity constraint value, the control module controls the combined converter to unload the fuel balls.

The invention provides a method for loading radionuclides in a micro-nano structure. The method comprises the following steps: preparing radionuclide nanoparticles; performing hydrophobic treatment on the micro-nano structure; the radionuclide nanoparticles are loaded into the micro-nano structure through dielectrophoresis; and curing the radionuclide nanoparticles.

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.

Some aspects are generally related to gripper systems for manipulating holders and / or containers disposed therein for use with radionuclide generators. In some embodiments, the gripper system further facilitates the insertion and / or removal of a stopper from the container, which may maintain a sterility of an interior of the container before and / or after exposure of the container to radionuclides from the radionuclide generator.

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.