108 results about "Isotope" patented technology

Main characteristic of the invention is the exploitation of the very large flux of high energy neutrons generated in a nuclear fusion tokamak with beam-driven plasma for the purpose of producing radioisotopes. It specifically relates to the deployment of precursor materials into the core of a nuclear fusion tokamak with beam-driven plasma for the purpose of exposing these materials to the neutron flux generated in the plasma by the process of nuclear fusion of Deuterium (D) and Tritium (T) to generate radioactive isotopes, so-called radioisotopes. The precursor materials contained in metallic capsules are incorporated into the blankets that surround the plasma.

The invention discloses a gas target device for isotope production, and the gas target device comprises a seat body which is provided with a channel; the water-cooled jacket body is mounted on the seat body, and the water-cooled jacket body is provided with a water-cooled cavity for circulating a water-cooled medium; the target body is installed on the base body and comprises a target body, the target body is located in the water cooling cavity and is provided with a target cavity, and the target cavity, the channel and the accelerator beam leading-out port are sequentially arranged in the set direction. According to the gas target device for isotope production disclosed by the embodiment of the invention, the water-cooled jacket body is arranged for cooling the target body, so that the target body is prevented from being damaged due to overhigh temperature of the target gas, the target gas can receive beam irradiation with higher flow intensity, and the isotope yield is improved.

The invention relates to the design, configuration and operation concept of a system, herein called radioisotope recovery system, to deploy and recover different precursor materials into and from the core of a nuclear fusion tokamak with beam-driven plasma for the purpose of exposing these materials to the neutron flux generated in the plasma by the process of nuclear fusion of D and T ions, which will cause the generation of radioactive isotopes (also called radioisotopes). Main characteristics of the invention are (i) a closed loop that circulates precursor materials into and out of a nuclear fusion tokamak with beam-driven plasma, (ii) the compliance of the system with the design and maintenance of a nuclear fusion tokamak with beam-driven plasma.

This invention provides an application of ion emitters based on covalent organic framework materials in thermal ionization mass spectrometry (TIEMS), specifically for improving the ionization efficiency of uranium during TIEMS measurements. Compared to conventional dual-band source modes in TIEMS, and ionization enhancement techniques such as graphite methods, benzene vapor carburizing methods, and graphene oxide methods, this invention significantly improves uranium ionization efficiency, facilitating the accurate measurement of ultra-trace and low-abundance uranium isotopes.

The invention belongs to the technical field of nuclear material measurement and analysis, and particularly relates to a neutron detection method for measuring the mass of a nuclear material and a radiation dose field of the nuclear material. According to the embodiment of the invention, the method comprises the steps: carrying out the energy response calculation and calibration of a detector through a parallel beam standard neutron source, and obtaining a calibration factor; performing energy response calculation and calibration on the detector by taking a to-be-measured object as a target object, determining the energy response and fluence-ambient dose equivalent conversion coefficient of the detector in a radiation field of the to-be-measured object, and realizing simultaneous measurement of a neutron counting rate, a fluence rate and an ambient dose equivalent rate; and the requirements of carrying out radiation dose field monitoring while carrying out quantitative analysis on the to-be-detected object in a special scene are met. The technical scheme of the invention can be popularized and applied to fixed-point monitoring of a to-be-detected system with known or measurable nuclear material source item composition and isotope abundance in nuclear facilities, or retention volume analysis and radiation dose measurement before transfer or treatment of some equipment for treating nuclear materials.

The invention relates to the technical field of isotope batteries and discloses a preparation method of a substrate-free radioactive isotope source and a preparation method of an isotope battery, the preparation method of the substrate-free radioactive isotope source comprises the following steps: S1, preparing an intermediate layer on the surface of a substrate, the intermediate layer comprising solvent atoms and solute atoms; s2, preparing a solute layer on the surface of the intermediate layer, wherein the solute layer comprises the solute atoms; s3, the middle layer and / or the substrate are / is heated, the solute atoms migrate to the middle layer, and a mixed layer is obtained; s4, preparing a loading layer on the surface of the mixed layer; and S5, transferring to a radioactive isotope source loading device, powdering the mixed layer, separating the loading layer from the substrate, and obtaining the substrate-free radioactive isotope source after the loading layer absorbs the radioactive elements. According to the preparation method of the substrate isotope source, the substrate and the isotope source can be separated to obtain a substrate-free isotope source.

The invention discloses a Beta radioactive isotope coating and magnetic confinement enhanced air-breathing electric propulsion ionization method. The method is characterized by comprising the following steps: selecting a plasma generation assembly without electrode discharge; the ionization is enhanced by adopting Beta radioactive isotope; arranging a magnetic field in the beta ray radiation direction to carry out magnetic field constraint; by dynamically adjusting the magnetic induction intensity and regulating and controlling the plasma state and the ionization rate, the Beta radioactive isotope (such as nickel-63) is creatively adopted, and the device has the advantages that the service life is long, the protection requirement is low, and mechanical compression and heating cannot induce nuclear reaction. And the requirement on the activity of the radioactive source is fundamentally reduced, so that the material cost and the safety risk are greatly reduced, and the practicability and the safety of the electric propulsion system are improved.

This invention provides an apparatus, system, and method for analyzing altered carbonate carbon isotopes. The apparatus includes: an enrichment component comprising at least one enrichment tube having an enrichment section; and a freezing component comprising a container filled with a refrigerant. The enrichment section is completely immersed in the refrigerant to freeze the target gas generated by sample decomposition within the enrichment section to a target concentration. Based on the technical solution of this invention, analysis of low-content altered carbonate carbon isotopes can be achieved; it can also simultaneously acquire multiple sets of samples required for altered carbonate carbon isotope analysis, saving time for detecting large quantities of altered carbonate carbon isotopes. Furthermore, the operation is simple, reducing analytical costs and providing a reliable technical means for the application of geochemical exploration technology.

The application provides a fuel and a method for increasing the neutron source intensity of a nuclear reactor, wherein the abundance of O in the fuel is 1% to 50% 18 O is 1% to 50%, and alpha particles and the enriched 18 O can significantly enhance the initial neutron source intensity of a nuclear reactor core in a pressurized water nuclear power plant, and help to improve the start-up performance and reduce the dependence on external neutron sources. In the passive start-up mode without using an external neutron source, the application improves the isotope abundance of O in the fuel, and improves the (alpha, n) reaction neutron source in the nuclear reactor core in the pressurized water nuclear power plant. 18 O in the fuel, and improves the isotope abundance of O in the fuel, and improves the (alpha, n) reaction neutron source in the nuclear reactor core in the pressurized water nuclear power plant.

An X-ray scanning system includes: a housing configured to be handheld; an X-ray source for scanning a target; a set of first detectors configured to be mechanically coupled to the housing and to detect resulting X-rays received from the target responsive to scanning the target; a second detector configured to be mechanically coupled to the housing; and a set of processors mechanically coupled to the housing and communicatively linked to the first detector and to the second detector so as to receive first and second signals, respectively, therefrom. The processor(s) are configured to: generate an image of the target based on the first signal; distinguish, in the second signal, a contribution of passive nuclear radiation detected at the second detector; and provide an output corresponding to the contribution of passive nuclear radiation. A related system for identifying a radioactive isotope, along with corresponding methods, are provided.

The present application relates to the technical field of isotope production equipment, and particularly relates to a target capsule facilitating replacement of target material and a target material replacement method. The target capsule comprises: a first shell provided with a first recess, the opening of the first recess being located at the first end face of the first shell; a second shell provided with a second recess, the opening of the second recess being located at the first end face of the second shell; and a target material for receiving bombardment of high-energy particles to generate isotopes; wherein the first shell is embedded in the second recess and is threadedly connected with the second shell, the target material is installed in the first recess, and the bottom wall of the second recess covers the opening of the first recess. In the present application, the sealing structure of the target capsule is optimized to be the first shell and the second shell connected through a threaded structure, so that workers can conveniently assemble, disassemble and replace the target material of the target capsule, the sealing structure can be repeatedly used, and the production efficiency of isotopes is improved.

The invention provides a rapid and high-precision determination method for reduction-state Os isotope. The method comprises the following steps: selecting a sample to be detected and carrying out ultrafine crushing; weighing the ground to-be-detected sample, and sealing and dissolving the sample; taking out the dissolved to-be-detected sample, and adding isometric hydrobromic acid to convert oxidation state Os into reduction state Os; carrying out acid removal and constant volume on the reduced-state Os solution; establishing a cup structure for static determination of the Os isotope, and performing MC-ICP-MS determination of the reduction state Os isotope according to the cup structure. According to the present invention, the dissolved to-be-tested sample is creatively taken out, and the isometric hydrobromic acid is added so as to convert the oxidation state Os into the reduction state Os, such that the memory effect can be substantially reduced, the efficiency can be improved, the research cost and the research time can be reduced when the MC-ICP-MS is adopted to rapidly and precisely measure the Os isotope, and the method is suitable for the mass sample test.

The invention relates to the technical field of radioactive isotope preparation, and provides dissolving and alkali adjusting equipment which comprises a melting device, a dissolving device, an alkali adjusting device, a pumping device and a control system, and the melting device is used for melting a target material in a sealed capsule target piece; a dissolving cavity and an opening communicated with the dissolving cavity are formed in the dissolving device, and the molten target material can enter the dissolving cavity from the opening and is dissolved in the dissolving cavity; an alkali adjusting cavity communicated with the dissolving cavity is formed in the alkali adjusting device, and a dissolving solution of the target material can be adjusted to be alkaline in the alkali adjusting cavity; the pumping device is used for pumping a dissolving agent to the dissolving cavity, pumping an alkaline agent to the alkali adjusting cavity and pumping a dissolving solution of a target material to the alkali adjusting cavity; the control system is configured to be capable of adjusting melting parameters of the melting device, dissolving parameters of the dissolving device, alkali adjusting parameters of the alkali adjusting device and pumping parameters of the pumping device. According to the dissolution and alkali adjustment equipment provided by the invention, irradiation damage to operators can be reduced.

The invention relates to a single event effect sensitivity detection method and device, equipment and a storage medium. The method comprises the following steps: acquiring a to-be-analyzed area of a to-be-detected sample; emitting a primary ion beam to the to-be-analyzed area through a secondary ion mass spectrometer; the primary ion beam is used for exciting an area to be analyzed to generate secondary ions; determining the target signal intensity of the to-be-analyzed area according to the mass-to-charge ratio and the signal intensity of the secondary ions received by the secondary ion mass spectrometer; and under the condition that the boron-10 isotope content corresponding to the target signal intensity is higher than a preset threshold value, determining that the to-be-detected sample is sensitive to the thermal neutron single event effect. By adopting the method, the detection cost can be reduced while the detection accuracy is ensured.

The invention relates to the technical field of isotope batteries and discloses a nanopore-containing power generation assembly. The nanopore-containing power generation assembly comprises a transduction layer, the loading layer is arranged on the surface of the transduction layer in advance, and the loading layer is provided with preset nanopores. The technical problem that in the preparation process of the radioactive source in the isotope battery, due to the fact that the hydrogen absorption temperature of a hydrogen storage material is high, large thermal mismatching exists between a transducer device and the hydrogen storage material, growth stress is generated in the phase change process, and consequently the transducer device may have serious structural damage can be solved; the loading layer arranged on the surface of the transduction layer in advance is adopted, and the loading layer is provided with the nanopore structure, so that when the loading layer serves as a basic structure for preparing the isotope power generation assembly, for example, nanopores are filled with radioactive gas such as tritium, the loading layer structure is stable, and the isotope power generation assembly is prepared. The probability that the energy conversion layer structure is damaged due to growth stress generated in the phase change process can be reduced, and then it is guaranteed that the structure of the prepared isotope power generation assembly is stable.

The invention provides an iron-sulfur isotope equilibrium fractionation factor calculation method based on a density functional theory. The iron-sulfur isotope equilibrium fractionation factor calculation method comprises the following steps: firstly, constructing initial mineral models of amorphous FeS, cubic FeS, maquinol ore, hematite, hematite and pyrite; the model is optimized through a spin polarization DFT + U method, GGA-PBE functional, OTFG ultra-soft pseudo potential, 400 eV plane wave cutoff energy and 5.0 * 10 <-7 > Hartree self-consistent field convergence standards are selected as calculation parameters, and the optimal Hubbar Ueff value and magnetic sequence arrangement of each mineral are determined; and finally, calculating the simple harmonic vibration frequency of the mineral, and deducing equilibrium fractionation factors (1000ln beta value) of Fe and S isotopes at a specific temperature. According to the method, the theoretical blank of isotope fractionation of the conversion path from amorphous FeS to pyrite is filled up, the data can be used for judging the isotope balance of minerals and tracing the mineralization process, and an important theoretical basis is provided for research on sedimentary diagenesis and ancient ocean redox.

The inventors have developed technology to improve the generation of daughter isotopes for clinical treatments. The technology includes systems and methods for using a liquid target to deliver parent isotopes to a reactor for neutron bombardment and subsequently separating desired daughter isotopes from the liquid target. According to an aspect of the technology described herein, a method of obtaining desired daughter isotopes comprises pumping a liquid target solution comprising a parent isotope through a fluid path that includes a first portion that passes through a fission reactor, a second portion that passes through a pump, and a third portion that passes through an isotope capture device.

The invention discloses an isotope source tracing analysis system based on fourth-century loess, and relates to the technical field of data processing. Fourth-century loess sample data is acquired and preprocessed, and a standardized data set is constructed; establishing a three-dimensional feature tensor based on the standardized data set, performing dimensionality reduction, calculating information entropy, dynamically distributing adaptive weights of all modes, weighting to obtain a coupling feature vector, and outputting the coupling feature vector and a weight distribution result; receiving a coupling feature vector and a weight distribution result, taking a multi-isotope end member value as a constraint, and outputting a contribution proportion of each potential source region through a Bayesian mixed linear model and constraint optimization solution; and receiving the contribution ratio, combining the isotope fractionation effect and a distance attenuation model, matching an optimal object source migration path by constructing a path cost function, and outputting migration path parameters. The invention provides a material source tracing analysis system which adopts multi-source indexes and is high in accuracy and high in quantification capability.

The invention provides a high-temperature reactor with an isotope production pore channel and a target loading and unloading method, the high-temperature reactor with the isotope production pore channel comprises a pressure container, a top plate, a bottom shielding layer, a conveying pipe, a loading and unloading device and a storage container, the pressure container is internally provided with a target channel, and the target channel penetrates through the top and the bottom of the pressure container in the vertical direction; the metal reactor internals, the carbon reactor internals and the graphite reactor internals penetrate through the pressure vessel; the top plate is arranged above the pressure container, and the bottom shielding layer is arranged at the bottom of the pressure container; the conveying pipe is inserted into the target channel and is used for conveying the target; the loading and unloading device is arranged at the upper end of the top plate, the storage container is arranged below the bottom shielding layer, and the lower end of the conveying pipe extends into the storage container. According to the invention, the target piece can stably stay in the reactor for irradiation, so that the target piece in the conveying pipe obtains enough neutron flux, and the device is convenient to assemble and disassemble.

A target support for isotope production includes a target cylinder with an inner flow channel and an end cap. The inner wall of the end of the target cylinder has a radially inner boss. The end cap has a fixed locking foot and a rotating locking foot, which can respectively engage with the inner boss. The fixed locking foot of the end cap is disposed on a cover plate of a fixed part, and the rotating locking foot is disposed on a rotating chuck. The rotating chuck can rotate relative to the cover plate to form a free position or a locked position. In the free position, axial rotation of the end cap ensures that both the fixed locking foot and the rotating locking foot are located within the gap of the inner boss. In the locked position, axial rotation of the end cap ensures that at least some of the fixed locking foot and / or the rotating locking foot are always engaged with the inner boss. This target support for isotope production has a simple structure, high reliability, and can be reused for a long time, reducing isotope production costs and decreasing the generation of radioactive waste.

The invention discloses a natural hydrogen formation cause identification method based on cluster isotope, which comprises the following steps: obtaining a purified hydrogen sample to be detected through separation and purification treatment; performing cluster isotope measurement on the purified hydrogen sample to obtain a cluster isotope value representing the abundance deviation random distribution degree of the dideuterium molecules; when it is judged that the cluster isotope value is in the original thermodynamic equilibrium state, the formation temperature of the purified hydrogen sample is inverted according to the theoretical function relation between the cluster isotope value and the thermodynamic equilibrium temperature; and comparing the formation temperature with a pre-established formation temperature range of different cause types of natural hydrogen, and determining the cause type of the purified hydrogen sample. According to the method, the cluster isotope delta DD is introduced as an anti-interference core index, and multi-source information verification and temperature quantitative inversion are combined, so that a fundamental breakthrough of the natural hydrogen cause from qualitative speculation to accurate quantitative judgment is realized.

The invention relates to the technical field of nuclear material analysis, in particular to a plutonium solution specific activity determination method and application, and the plutonium solution specific activity determination method comprises the following steps: taking a plutonium solution with known specific activity A1 as a standard solution, determining the liquid flash counting rate of the standard solution, and recording the liquid flash counting rate as C1; obtaining a second-order conductance spectrum of the standard solution by using an ultraviolet-visible absorption spectrum method, determining the peak area of a characteristic absorption peak of tetravalent plutonium in the second-order conductance spectrum of the standard solution, and recording the peak area as S1; measuring the liquid flash counting rate of the to-be-measured solution, and recording the liquid flash counting rate as C2; obtaining a second-order conductance spectrum of the to-be-detected solution by using an ultraviolet-visible absorption spectrometry, determining the peak area of a characteristic absorption peak of tetravalent plutonium in the second-order conductance spectrum of the to-be-detected solution, and recording the peak area as S2; and calculating the specific activity A2 of the solution to be detected according to the following formula. According to the method, liquid scintillation counting and ultraviolet-visible spectrophotometry are combined, so that combination of activity response and concentration response is realized, and acquisition of isotope composition of a plutonium solution to be detected and complex sample pretreatment are not needed.

This invention discloses a gas purification device for neutron-activated argon isotope dating based on a D-D accelerator, belonging to the field of rare gas isotope mass spectrometry analysis and geological dating technology. Addressing the limitations of traditional gas purification systems, which suffer from large internal volumes and high static release rates, making them unsuitable for the efficient purification and enrichment of trace argon isotopes generated by the D-D accelerator neutron activation method, this invention employs an integrated 316L stainless steel substrate, internally integrating a main gas flow channel and multiple branch channels. The substrate houses a sample gas injection module, a primary purification module, a secondary purification module, a tertiary purification module, a vacuum preparation and monitoring module, a standard gas injection module, and a gas enrichment module. Each module is connected to the main gas flow channel via branch channels, achieving multi-stage purification of the mixed gas and low-temperature enrichment of trace argon isotopes. This device is used for gas purification in D-D accelerator neutron-activated argon isotope dating, meeting the requirements for efficient purification and enrichment of extremely small amounts of argon gas.

The invention relates to an isotope neutron source reference radiation device based on pneumatic transmission, and a radioactive source exchange assembly comprises a radioactive source rotating disc which is in a disc shape, is uniformly provided with a plurality of neutron source storage positions along the circumferential line, and rotates to replace a to-be-detected neutron source; one end of the radioactive source pneumatic transmission pipeline is aligned with the storage position of the to-be-detected neutron source on the radioactive source turntable, and the other end is connected with the irradiation device; the radioactive source pneumatic transmission pipeline is perpendicular to the ground; the pneumatic transmission gas inlet pipeline is arranged below the storage position of the to-be-detected neutron source on the radioactive source turntable, one end of the pneumatic transmission gas inlet pipeline is aligned with the storage position of the to-be-detected neutron source on the radioactive source turntable, and high-pressure gas is introduced into the other end of the pneumatic transmission gas inlet pipeline. The device achieves the purposes of storing a plurality of neutron sources based on the radioactive source turntable, rotating and replacing different neutron sources to align with the radioactive source pneumatic transmission pipeline, and pushing the to-be-detected neutron source through the high-pressure gas, thereby achieving the technical effects that the plurality of neutron sources can be placed in the device, and the pushing speed of the high-pressure gas is relatively high.

The invention relates to the technical field of electromagnetic separation, and provides a receiving pocket, a receiver and an isotope electromagnetic separator. The receiving pocket comprises a pocket body, a supporting assembly and an electrode plate, a receiving opening communicated with the inner space of the pocket body is formed in the pocket body, a penetrating opening is formed in the electrode plate, the electrode plate is used for being connected with an external power source, and the supporting assembly is connected between the pocket body and the electrode plate so that the penetrating opening can be aligned with the receiving opening. According to the receiving pocket, the receiver and the isotope electromagnetic separator provided by the invention, the ion beam current can be collected.

The invention relates to the technical field of isotope production hot chambers, in particular to a target station hot chamber system for isotope production and an operation process of the target station hot chamber system. The target station hot chamber system comprises an operation hot chamber used for executing a target feeding process, a target discharging process and a discharging process; the irradiation chamber is used for executing an irradiation process; the target vehicle channel is used for communicating the irradiation chamber with the operation hot chamber; wherein the target vehicle channel comprises a track and a target vehicle, the track extends from the operation hot chamber to the irradiation chamber, and the target vehicle conveys a target container along the track. According to the invention, through functional partition design and system arrangement of the hot chamber, the target vehicle is used for operating the target device between the irradiation chamber and the operation hot chamber, and meanwhile, the automatic system in the operation hot chamber is used for carrying out target loading and unloading operation, so that batch cross-hot-chamber transfer of the target sheets can be realized; and the process target loading and unloading requirements and the high-efficiency circulation of materials in the hot chamber can be met, and the requirements of isotope batch production are met.

The invention relates to the technical field of vacuum detection, in particular to an efficient detection device for a vacuum chamber of an isotope electromagnetic separator. Supporting legs are fixed at the bottom of the detection platform; a rotating seat is arranged at the top of the detection platform, and a placing table is fixed at the top of the rotating seat; a rotating groove is formed in the top of the detection platform, a rotating block is rotationally installed in the rotating groove, and the rotating seat is fixed to the top of the rotating block. Two modes can be adopted for detecting the vacuum chamber, the vacuum chamber with obvious defects can be visually detected in a manual detection mode, and the detection efficiency is improved. The intelligent detection mode can detect the vacuum chamber without obvious defects, on one hand, the two detection modes are combined to effectively improve the detection efficiency of the vacuum chamber, and on the other hand, the two detection modes are combined to ensure the detection precision of the vacuum chamber.

This invention belongs to the field of nuclear radiation detection and nanomaterials technology, specifically relating to a submicron-resolution boron-10 isotope-enriched boron nitride neutron scintillator. Addressing the technical bottleneck of severe light scattering in existing physically hybrid scintillators, this invention innovatively employs anodized aluminum nanopore templates as a confined reaction vessel and optical waveguide structure. A precursor solution enriched with boron-10 isotopes is filled into the template pores, and a hexagonal boron nitride scintillator with a nanoarray structure and boron-10 isotope enrichment is generated through in-situ reaction at high temperature. This structure strictly confines the generation and propagation of scintillating light within independent nanopillars, fundamentally suppressing transverse light scattering by utilizing the waveguide effect of the pore walls. Thus, while ensuring the macroscopic thickness of the scintillator and high neutron absorption efficiency, it achieves micron- to submicron-level spatial resolution.

The present application relates to the technical field of isotope production, and particularly relates to a welding-free target capsule for isotope production and a manufacturing method thereof. The welding-free target capsule comprises: a target material for generating isotopes under high-energy particle bombardment; a first metal film covering one side of the target material; and a second metal film covering the other side of the target material; wherein the first metal film and the second metal film are made of a material with ductility; and the edges of the first metal film and the edges of the second metal film are attached to the outer circumferential side of the target material and folded into a ring-shaped sealing structure. In the present application, the metal film with good ductility is used as the cladding material of the target material, and the sealing structure is formed by folding the connecting part of the metal film, which can not only ensure efficient heat dissipation of the target capsule in a water-cooled environment, but also improve the manufacturing method of the sealing structure, so that the manufacturing steps of the sealing structure are simple and easy to implement, thereby reducing the manufacturing cost of the target capsule.