334 results about "Isotope" patented technology

The invention relates to the technical field of isotope production, in particular to a welding-free target capsule for isotope production and a manufacturing method of the welding-free target capsule. The welding-free target capsule comprises a target material used for generating isotopes under bombardment of high-energy particles; the first metal film covers one side of the target material; the second metal film covers the other side of the target material; wherein the first metal film and the second metal film are made of materials with ductility; the edge of the first metal film and the edge of the second metal film are attached to each other on the peripheral side of the target material and are folded into an annular sealing structure. In the invention, the metal film with good ductility is used as a coating material of the target material, and the sealing structure is formed by folding the connecting part of the metal film, so that the target capsule can be ensured to efficiently dissipate heat in a water-cooling environment, the manufacturing mode of the sealing structure can be improved, the manufacturing steps of the sealing structure are simple and easy to implement, and the manufacturing cost of the target capsule is further reduced.

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 method for accurately deducting Sr double-charge interference in in-situ Ca isotope determination, and relates to the technical field of isotope analysis. According to the method, the Sr double-charge interference in the in-situ Ca isotope measurement is accurately deducted through an iteration method, the Ca isotope measurement result can be simply and quickly corrected, and high-resolution, low-detection-limit and high-flux Ca isotope measurement is realized; ca single-charge fractionation factors are calculated through an iterative method, and instrument quality discrimination correction and accurate deduction of Sr double-charge interference are simultaneously realized through formulas 1-5 in combination with the Sr isotope ratio; the method breaks through the application limitation of in-situ Ca isotope measurement, is suitable for high-Sr and low-Sr samples, solves the technical problems of in-situ Ca isotope analysis accuracy and analysis precision, fills the technical blank of Ca isotope measurement in the Sr-rich sample in laser in-situ detection, and provides a firm technical support for application in the field of geoscience.

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 present invention relates to a device-produced medical isotope 225 Photonuclear reaction preparation in Ac production technology 225 Ac radium target design, specifically involving a method for producing 225 Ac's 226 Ra isotope target and its application. 226 The Ra isotope target comprises a nickel substrate, 226 Ra isotope sample, nickel electroplating layer and nickel protective shell; wherein, 226 The Ra isotope sample is evenly concentrated in the center of the nickel substrate, and the nickel electroplating layer covers 226 The outer surface of the Ra isotope sample, and the nickel substrate and nickel electroplating layer will 226 The Ra isotope sample is wrapped in the middle; the nickel protective shell wraps the nickel electroplating layer. 226 Ra isotope targets can be used in electron linear accelerators as a photonuclear reaction production 225 Ac raw material target, can improve 225 Production of Ac isotopes.

The invention provides an isotope production method based on irradiation of a side reflecting layer of a pebble-bed high-temperature gas cooled reactor. The method comprises the following steps: transforming a neutron source duct and a physical starting device duct in the side reflecting layer of the pebble-bed high-temperature gas cooled reactor; designing an isotope target on the basis of the production requirement of the isotope to be produced and the reconstructed pore parameters, and adjusting the isotope target according to the safety analysis result of the isotope produced by online irradiation of the side reflecting layer; designing an isotope irradiation device for carrying out in-pile and out-pile operation on the isotope target, and calculating isotope irradiation theoretical parameters; and loading an isotope target into the modified pore channel through an isotope irradiation device, performing online irradiation according to isotope irradiation theoretical parameters, and discharging the isotope target after irradiation is completed. According to the method, the radioactive isotope is generated through online irradiation of the side reflecting layer of the pebble-bed high-temperature gas cooled reactor, so that the application scene of the reactor is enriched, and the utilization efficiency of the reactor is improved.

The invention relates to the design of a radium target for preparing 225Ac through a photo-nuclear reaction in the technical field of production of a mechanical produced medical isotope 225Ac, in particular to a 226Ra isotope target for producing 225Ac and application of the 226Ra isotope target. The 226Ra isotope target comprises a nickel substrate, a 226Ra isotope sample, a nickel electroplated layer and a nickel protective shell; wherein the 226Ra isotope samples are uniformly concentrated at the central position of the nickel substrate, the nickel electroplated layer covers the outer surfaces of the 226Ra isotope samples, and the nickel substrate and the nickel electroplated layer wrap the 226Ra isotope samples in the middle; and the nickel protective shell wraps the nickel electroplated layer. The 226Ra isotope target can be applied to an electron linear accelerator and can be used as a raw material target for producing 225Ac through a photo-nuclear reaction, and the production quantity of the 225Ac isotope can be increased.

The invention provides a safety analysis method and system for isotope irradiation production of a high-temperature gas cooled reactor, and the method comprises the steps: building a reactor core model of a pebble-bed high-temperature gas cooled reactor and a target model of a selected target type based on a formulated target irradiation scheme; calculating reactor core states under various working conditions based on the reactor core model and the target model to obtain reactor core key parameters; judging whether the reactor core key parameters belong to a safety range or not, and under the condition that the reactor core key parameters belong to the safety range, performing accident development sequence calculation based on the reactor core key parameters to obtain a simulated accident result; judging whether the simulation accident result is enveloped by a safety accident in the final safety analysis report of the high-temperature gas cooled reactor or not, and obtaining a safety analysis result of isotope irradiation production of the high-temperature gas cooled reactor under the condition that the simulation accident result is enveloped by the safety accident in the final safety analysis report of the high-temperature gas cooled reactor. And how to carry out physical and thermal safety analysis of isotope irradiation production of the pebble-bed high-temperature gas cooled reactor is determined.

The present invention relates to the technical field of isotope production equipment and provides a target device for isotope production based on a high-current particle accelerator, comprising: a target chamber and a target assembly; the target chamber having an inner cavity and a side facing the beam having a plurality of beam holes arranged in an array, the beam holes being covered with target windows; the target assembly comprising a target frame; the target frames being arranged in a one-to-one correspondence with the target windows, and at least one mounting position for a target capsule being provided in the target frame in the axial direction of the beam holes; openings being provided on both sides of the target frame, and a plurality of target frames arranged in a preset direction forming a group; the side openings of the target frames in the same group corresponding to each other and forming independent coolant flow channels with the inner wall of the target chamber; each target capsule having a gap on both sides along the axial direction of the beam hole for coolant to flow through; and a plurality of water inlet holes and water outlet holes corresponding to the plurality of coolant flow channels being provided on both sides of the target chamber. This arrangement can effectively reduce the temperature rise of the target material under high beam intensities, enabling isotope production at beam intensities above the milliampere level.

The invention provides a method for quantitatively evaluating the storage condition of magma hydrothermal deposit based on thermochronology, which comprises the following steps: determining a sample sampling point based on field geological survey, collecting typical samples, picking out zircon and apatite monominerals, and preparing a U-Pb isotope test target and a fission track test optical slide; carrying out fission track dating on the zircon and the apatite to measure the U-Pb isotope age and (U-Th) / He isotope age of the zircon and the apatite; thermal history evolution process simulation is carried out by integrating test data, and finally, the deposit preservation condition is quantitatively calculated and evaluated according to simulation. According to the method, a scientific quantitative full-chain research scheme is provided for augmentation, denudation and thermal history evolution research of the magma hydrothermal deposit, and the technical problem of quantitative evaluation of the storage condition of the magma hydrothermal deposit is solved.

The invention provides a high-quality boron isotope separation process and device, the device comprises an exchange rectification system, a complexing system, a complex cracking system and a boron-11 refining system, natural abundance boron trifluoride isotopes are separated through an exchange rectification tower, and cyclic regeneration of boron trifluoride and anisole is realized by adopting the complexing system and the cracking system. A boron-11 refining system is arranged to further improve the abundance of boron-11. According to the method, the industrial continuous production of the high-quality boron trifluoride-10 with the abundance of 99% and the high-quality boron trifluoride-11 with the abundance of 99.9% can be synchronously realized, the process is simple and clear, and the operability is high.

The invention belongs to the technical field of production of isotopes by a sodium-cooled fast reactor, and aims to solve the problems that the moderation effect is limited, the reactor core disturbance is relatively large and fast neutron energy spectrum is not beneficial to the production of the ultra-uranium isotopes during the production of the ultra-uranium isotopes. The invention provides a method for producing a super-uranium isotope by using a sodium-cooled fast reactor and a sodium-cooled fast reactor core. According to the method, moderator assemblies and super-uranium isotope production assemblies are arranged on a first circle of a radial conversion area in a flower arrangement mode, the super-uranium isotope production assemblies are arranged on a second circle of the radial conversion area, and the side, facing the center of the reactor core, of the first circle is coated with a thermal neutron absorption material; the reactor core is provided with a radial conversion area, moderator assemblies and super-uranium isotope production assemblies are arranged on a first circle of the radial conversion area, the super-uranium isotope production assemblies are arranged on a second circle of the radial conversion area, and thermal neutron absorbing materials are arranged on the side, facing the center of the reactor core, of the first circle. The super-uranium isotope is concentrated in the radial conversion region for production, the moderation effect is good, the disturbance to the reactor core is small, and the productivity is high.

The invention relates to a synthetic standard sample suitable for in-situ pyrrhotite Fe-S isotope analysis and a preparation method and application thereof, and belongs to the technical field of geological analysis and material analysis. The particle size of the synthesized standard sample is 100-150 microns, and the interior of the particle is compact and free of holes; delta 34S is equal to-1.16 + / -0.22 per mill, and delta 56Fe is equal to 0.39 + / -0.03 per mill; the delta 34S in the synthesized standard sample is detected by SIMS, and the standard deviation 2SD of the delta 34S is 0.53%. The delta 56Fe in the synthesized standard sample is detected by LA-MC-ICPMS, and the standard deviation 2SD of the delta 56Fe is equal to 0.47 per mill. The method has the advantages that the pyrrhotite is synthesized in a laboratory, the reproducibility of the synthesized standard sample is realized, and the problems that the original in-situ pyrrhotite Fe-S isotope standard sample is natural in source, very few in available quantity and non-reproducible are solved.

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.

The present application relates to a kind of neutron energy spectrum optimization method and system for improving reactor radioisotope production efficiency, method includes the following steps: initial population of genetic algorithm is randomly generated, these population individuals are all neutron energy spectrum divided into n energy group, the body average neutron energy spectrum in target piece when the neutron energy spectrum of each individual is calculated as irradiation hole incident spectrum, the radioisotope production under the body average neutron energy spectrum in target piece corresponding to each individual is calculated, the evolution of population is realized by the mutation and crossing operation of genetic algorithm, the above-mentioned process is repeatedly executed until iteration converges, obtains the neutron energy spectrum regulation scheme for realizing the maximization of radioisotope production.Compared with prior art, the present application efficiently realizes the accurate regulation of neutron energy spectrum in reactor, can provide technical support for the energy spectrum regulation process of radioisotope irradiation production in reactor.

A method and apparatus for producing radioisotopes. The method includes generating fast neutrons by irradiating a neutron producing target with a deuteron beam from a deuteron accelerator. These fast neutrons directly irradiate a first sample. The fast neutrons that pass through the first sample undergo multiple-scattering by a neutron scattering material made of a light element positioned around both the neutron producing target and the first sample. This arrangement generates various radioisotopes simultaneously in large amounts from both the first sample and a second sample through nuclear reactions. The method enables production of multiple radioisotopes in a single process for applications in medicine, research, education, agriculture, and industry.

This invention provides a target loading device for producing short-half-life isotopes in a heavy water reactor, comprising a channel, an electric cylinder, and a target drum assembly. One end of the channel leads to the reactor core. The target drum assembly sequentially pushes the loaded targets to the target outlet. The main shaft of the electric cylinder is coaxially arranged with the target outlet, driving the main shaft to move towards the target outlet to push the target at the outlet into the channel. The target enters the reactor core through the channel. This invention enables the loading of short-half-life radioactive isotope targets for several days or tens of days during heavy water reactor power operation, facilitating installation and maintenance. Different types and quantities of isotope targets can be loaded into the core production channel during heavy water reactor power operation.

The application provides a yield optimization method, system and medium for isotope irradiation production in a research reactor, and relates to the technical field of nuclear research reactors. The yield optimization method comprises the following steps: obtaining design data of the research reactor, irradiation hole usage data range and total required number of at least one type of isotope target; constructing a research reactor Monte Carlo model associated with the research reactor according to the design data; determining a flux influence factor and a multi-group microscopic cross section corresponding to the at least one type of isotope target, and a target-free neutron flux field function according to the research reactor Monte Carlo model; and taking, as a yield optimization result, layout data of each irradiation hole corresponding to a preset isotope yield target through burnup calculation according to the irradiation hole usage data range, the total required number of irradiation holes, the flux influence factor and the multi-group microscopic cross section corresponding to the at least one type of isotope target, and the target-free neutron flux field function.

A system and method for producing radioisotopes such as molybdenum-99. The system comprises a first accelerator, a second accelerator, a first beamline, a second beamline, and a target. Using a pair of accelerators, beamlines are preferably fired at a target from opposite directions, thereby irradiating the target from both sides. The system can further comprise a target cooling system utilizing gaseous helium, a modular local target shielding comprised of boxes of either metal shot with liquid coolant or steel with concrete, and a hot cell for loading and unloading target disks.

A computer implemented method (200) comprising selecting one or more pairs of energy levels of an isotope of an ion for a qubit for a quantum computer, wherein each of the one or more pairs of energy levels comprises a first metastable state and a second metastable state.

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 utility model discloses a storage tank for deuterium isotope abundance detection, which comprises a tank body and a cover body, and two horizontal sides of the cover body are fixedly connected with support frames. The method comprises the following steps: putting a magnesium rod into a tank body from a magnesium rod putting opening, sealing, vacuumizing, injecting a water sample into a reaction container, heating the tank body, enabling the magnesium rod to react with the water sample to generate deuterium-labeled hydrogen, and sucking the deuterium-labeled hydrogen in the tank body after the reaction container is cooled to room temperature. The cover body and the tank body are both fixed with the support frame while normal detection of the deuterium isotope abundance is ensured, and the base at the bottom of the support frame is matched with the upper suction cup, so that stable connection between the storage tank and a working table can be ensured, deviation of the storage tank is avoided, and the storage tank is convenient to use. Therefore, the use stability of the storage tank for deuterium gas isotope abundance detection is improved.

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.

The invention relates to the technical field of metering, in particular to a determination method of an acetyl hexapeptide-8 standard substance and application of the acetyl hexapeptide-8 standard substance. The invention provides a method for measuring the purity value and the uncertainty of the acetyl hexapeptide-8 standard substance, the acetyl hexapeptide-8 standard substance is developed, the result can be traced to SI units finally, the blank in the prior art is filled, and the method has important significance for establishing a quality control and evaluation system of the acetyl hexapeptide-8 standard substance. According to the method, the acetyl hexapeptide-8 standard substance is jointly valued by adopting an isotope dilution mass spectrometry and a quantitative nuclear magnetic method, so that the accuracy and the reliability of a valuing result are improved.

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.

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.