456 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.

Aspects of the present disclosure may include a method and / or a system for identifying an ion chain having a plurality of trapped ions, selecting at least two non-consecutive trapped ions in the ion chain for implementing a qubit, applying at least a first Raman beam to shuttle at least one neighbor ion of the at least two non-consecutive trapped ions from a ground state to a metastable state, and applying at least a second Raman beam to one or more of the at least two non-consecutive trapped ions, after shuttling the at least one neighbor ion to the metastable state, to transition from a first manifold to a second manifold.

The invention relates to a method for measuring oxygen isotope of chromite by laser fluorination-gas mass spectrometry, which comprises the following steps: 1) sample screening: analyzing major elements and oxygen isotope of chromite to obtain a homogeneous sample: 2) mixing the chromite sample with oxygen-containing minerals, and analyzing oxygen isotope by laser fluorination-gas mass spectrometry; and 3) establishing a correction equation of the Cr2O3 content and the oxygen isotope delta < 18 > O difference value, and correcting the oxygen isotope delta < 18 > O value. According to the method, a certain amount of zircon is mixed into the chromite sample, so that the oxygen yield is remarkably improved, and the data of the test method are effectively corrected by utilizing a correction calculation equation between the delta < 18 > O difference value and the Cr2O3 content, so that the accuracy of oxygen isotope detection is improved.

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 utility model belongs to earth and planet chemical instrument equipment, and discloses a Nano-C isotope analysis device which comprises an element analysis system, a carbon dioxide freezing enrichment system and an isotope mass spectrometry system, the carbon dioxide freezing enrichment system comprises a six-way valve, the six-way valve is communicated with a first freezing assembly and a second freezing assembly, and the second freezing assembly is communicated with the isotope mass spectrometry system; the first freezing assembly comprises a first freezing container, and a first cold trap communicating with the six-way valve is arranged in the first freezing container in a liftable mode. The second freezing assembly comprises a second freezing container, and a second cold trap communicating with the six-way valve is arranged in the second freezing container in a liftable mode. The carbon isotope analyzer is simple and compact in mechanism, convenient to use, capable of analyzing carbon elements in different forms and accurately measuring isotope composition of carbon in different forms at the nanomole level, capable of enriching and purifying a sample to be detected for multiple times, capable of reducing analysis errors and capable of improving measurement sensitivity and precision.

The invention provides a neutron spectrum optimization method for improving the isotope irradiation production conversion rate, and relates to the technical field of reactor engineering. Monte Carlo modeling is performed on an isotope target and related mechanisms; then Monte Carlo critical calculation is carried out, and initial neutron energy spectrums are obtained respectively; next, on the basis of the initial neutron energy spectrum, neutron energy spectrum sensitivity analysis is carried out on the target isotope; on the premise that the total neutron flux is kept unchanged, an ideal neutron energy spectrum is obtained; comparing the difference between the initial neutron energy spectrum and the ideal neutron energy spectrum, and arranging a neutron filter around an isotope target in the Monte Carlo model; then, the material type of the neutron filter is replaced, neutron energy spectrums under different material types are calculated through Monte Carlo criticality, and the material type capable of improving the target nuclide conversion rate is determined; and finally, based on the determined neutron filter material type, obtaining an optimized neutron energy spectrum. The conversion rate of isotope irradiation, namely the production efficiency of isotopes, can be improved.

The disclosure provides a test device and a test method for isotope measurement of noble gases in lunar soil. The testing device includes a carbon dioxide laser ultra-high vacuum sample melting system, zirconium-aluminum getters, a vacuum dry pump, a first molecular pump, a second molecular pump, a neon gas capture unit, an argon gas capture unit, an argon krypton-xenon capture unit, a dilution tank, a sputtering ion pump and a noble gas mass spectrometer which are connected through pipelines, and each pipeline and each component are connected through a specific way; in addition, control valves for controlling the opening and closing of the pipelines are installed on the connection path between each pipeline and each component, and the disclosure also provides a matching test method.

The invention relates to an isotope receiving device for inert gas ion collection and a collection method. The isotope receiving device comprises a vacuum box and a receiving pocket which is arranged in the vacuum box and is used for receiving an inert gas ion beam; an entrance slit for an inert gas ion beam to pass through is formed in a front panel, directly facing the incident ion beam, of the receiving pocket, and a graphene window for the inert gas ion beam to penetrate through covers the entrance slit; a rear panel of the receiving pocket is connected with a vacuum displacement platform, a gas path pipeline communicated with an inner cavity of the receiving pocket is arranged in the vacuum displacement platform, and neutralized inert gas is output from the isotope receiving device along the gas path pipeline; and the receiving pocket is also connected with a driving assembly capable of moving back and forth along the incident direction of the ion beam. Compared with the prior art, the isotope receiving device provided by the invention can reduce gas escape after inert gas ions are neutralized, and can realize effective collection of the neutralized isotope inert gas.

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 discloses a crude oil parent material sedimentary environment identification method, and relates to the technical field of petroleum geological exploration. The invention relates to a crude oil parent material deposition environment identification method, which comprises: reference substance treatment: separating crude oil from different deposition environments, carrying out chromatography-mass spectrometry analysis and chromatography-isotope-mass spectrometry analysis on the separated product to obtain a Pr / Ph value and a 13C isotope of fluorene, and establishing an identification plate; sample treatment: separating the sample crude oil to be identified, and carrying out chromatography-mass spectrometry and chromatography-isotope-mass spectrometry on the separated product to obtain a Pr / Ph value and 13C isotope of fluorene; and sample identification: plumbing the Pr / Ph value of the crude oil sample to be identified and the 13C isotope of fluorene into the identification chart for identification. The method is less affected by secondary effects, the accuracy of crude oil parent material deposition environment analysis is improved, and deposition basin oil source comparison and oil-gas migration path research are facilitated.

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 relates to the technical field of isotope production equipment, in particular to a target device for isotope production, which comprises a target chamber and a target assembly, the target chamber is provided with an inner cavity, and a plurality of beam holes arranged in an array are formed in the face, facing beam current, of the target chamber. The beam holes are covered with target windows. The target assembly is inserted into the target chamber and comprises a target frame and a target capsule; the target frames and the target windows are arranged in a one-to-one correspondence manner, and at least one mounting position for mounting the target capsule is arranged in each target frame in the axial direction of the beam hole; openings are formed in the two sides of each target frame, the side openings of the multiple target frames correspond to one another and define an independent cooling liquid flow channel with the inner wall of the target chamber, and gaps are formed in the two sides, in the axial direction of the beam hole, of each target capsule and used for allowing cooling liquid to flow through. A detachable cover plate assembly is arranged at the top of the target chamber, and the target assembly is integrally sealed in the target chamber in an assembling state. The scheme is used for solving the defects that the target assembly is inconvenient to disassemble and assemble, the safety is low and the cooling water sealing is difficult to guarantee in a high-radiation dose environment.

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 isotope production, and particularly relates to a 177Lu irradiation production method based on a pressurized water reactor. Comprising the following steps: step 1, packaging Lu2O3 powder in a target box, performing sealing treatment, and storing the target box in a storage tank of a rabbit system outside a reactor core; 2, during the operation period of the pressurized water reactor, transporting the target piece box into the reactor core through a running rabbit system; 3, the target piece box receives neutron irradiation at the axial middle position of the central instrument pipe, and 176Lu reacts to generate 177Lu; 4, when the 177Lu generated by the irradiation of the 176Lu in the target box reaches the designed saturation specific activity, transporting the target box to a post-irradiation target storage tank outside the reactor core; and 5, during the operation period of the pressurized water reactor, repeating the steps 2-4 until the reactor is shut down. The method has the beneficial effects that the single irradiation time of the target boxes can be controlled through analysis, so that a plurality of target boxes can be irradiated in a single refueling period of the pressurized water reactor, and the yield of 177 Lu is greatly improved.

The invention relates to the technical field of isotope irradiation production, in particular to a target material arrangement device suitable for researching reactor irradiation production of iride-192. The target material arrangement device mainly comprises a cladding, a plurality of clamping blocks and iridium sheets, the clamping blocks are arranged on the inner side of the cladding and arranged around the circumference of the central axis of the cladding, and the iridium sheets are arranged on the clamping blocks; and the iridium sheet is arranged on one side, in contact with the cladding, of the clamping block. Through the structure, the target material in the target material arrangement mode of the iride-192 is designed into a pure I < r > circular sheet. The small-size target material can improve the irradiation uniformity of a single target material and can be used for manufacturing a small-size flaw detection source device, and the application range of a product is widened. The target material is defined as a natural target material and a high-enrichment-degree target material according to the difference of the content of the iridium 191 in the target material, the target material arrangement can be automatically adjusted according to the actual production requirement, and the production flexibility of the iridium 192 can be improved.

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 discloses a method for accurately measuring a nano ion probe olivine Mg isotope micro-region and applying a moon sample, particularly relates to application of a nano ion probe (SIMS) technology in magnesium isotope analysis, and particularly relates to a method for carrying out high-resolution and high-precision magnesium isotope analysis and on-line matrix effect correction by utilizing a nano ion probe (NanoSIMS). The method comprises the following steps: (1) synthesizing an olivine reference substance with a coverage Fo value (magnesium-iron ratio) range of 0-90 by using a high-temperature and high-pressure experimental method, and verifying composition uniformity and isotope stability of the olivine reference substance through an electron probe (EMPA) and a multi-receiving inductively coupled plasma mass spectrometry (MC-ICP-MS); (2) optimizing NanoSIMS instrument parameters, and realizing synchronous detection of 24Mg < + >, 26Mg < + >, 28Si < + > and 56Fe < + > through a static multi-collection mode; (3) based on the ratio of 24Mg / (24Mg + 56Fe), proposing a biphase Hill equation to correct the matrix effect, and realizing online correction; and (4) analyzing the geological sample by using the method, and revealing the chemical and isotope change characteristics of the micron scale. The method has high resolution (1 [mu] m) and high precision (0.4 per thousand to 0.6 per thousand), and is suitable for micro-area isotope analysis in the fields of planetary science and geochemistry.

The invention discloses an uncertainty determination method and device for nuclear material analysis, a medium and a program product. The method includes: acquiring a first set and a second set; wherein the first set comprises isotope analysis results obtained by analyzing the nuclear material through a destructive analysis method; the second set comprises isotope analysis results obtained by analyzing the nuclear material through a non-destructive analysis method; determining a data deviation between the first set and the second set; determining a random error of the non-destructive analysis method based on the data deviation; determining a system error of the non-destructive analysis method based on the data deviation; and determining the uncertainty of the non-destructive analysis method for the content of the isotope in the nuclear material based on the system error and the random error.

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.

Inorganic compounds having the formula LiMP2Q6, where M is Ga, In, Bi, Sb, As, Al, or a combination thereof, and Q is S and / or Se, are provided. Methods and devices for detecting incident neutrons and alpha-particles using the compounds are also provided. For thermal neutron detection applications, the compounds can be enriched with lithium-6 isotope (6Li) to enhance their neutron detecting capabilities.

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.