42 results about "Isotope separation" patented technology

The invention belongs to the field of medical isotope separation and preparation, and particularly relates to a method for separating and purifying < 212 > Pb from a thorium solution, which comprises the following steps: 1) leacheate is introduced into a Pb selective adsorption column to pretreat the Pb selective adsorption column, and then < 232 > Th salt solution and leacheate are introduced in sequence; 2) continuously introducing a desorption solution into the Pb selective adsorption column, enabling the desorption solution passing through the Pb selective adsorption column to flow into the Th selective adsorption column, and collecting the outflowing desorption solution; a desorption solution only containing 212Pb is obtained; according to the method, the 212Pb in the high-concentration thorium solution can be separated and purified at the same time. While < 232 > Th impurity entrainment and pollution in a < 212 > Pb product are remarkably reduced, compared with a single-column process, the separation time is basically not increased. The separated 212Pb product has high radionuclide purity and chemical purity at the same time, and can meet related pharmaceutical requirements.

The application provides a device for coupling xenon isotope separation and neon-helium purification separation and a use method thereof. Based on various non-low-temperature gas separation technologies, through multi-stage module cooperation, high-efficiency enrichment of xenon isotope raw material gas under non-low-temperature conditions and purification and purification of air separation crude neon-helium gas are coupled, including thermal coupling and intermediate material coupling. The crude neon-helium gas produced in the process is fully utilized, the energy consumption and operation complexity are significantly reduced, and the development advantage can be further improved.

The present invention relates to the field of distillation of isotopes by means of distillation columns. It is an object of the present invention to describe an innovative distillation column providing a significant improvement to the prior art. In particular, the distillation column will be a modular column with the innovative idea of any height required.

The invention relates to a gaseous hydrogen isotope separation device and system and a gaseous hydrogen isotope separation method, and belongs to the technical field of hydrogen isotope separation. The gaseous hydrogen isotope separation device comprises an anode gas diffusion layer, an anode catalyst layer, a proton exchange membrane, a cathode catalyst layer and a cathode gas diffusion layer which are sequentially stacked; the anode gas diffusion layer and the anode catalyst layer are positioned in an anode region of the gaseous hydrogen isotope separation device, and the cathode catalyst layer and the cathode gas diffusion layer are positioned in a cathode region of the gaseous hydrogen isotope separation device; the gas inlet and the first gas outlet are formed in the anode region; the second gas outlet is formed in the cathode region; the gas inlet is used for being communicated with hydrogen isotope mixed gas; the anode region is connected with the anode of a power supply, and the cathode region is connected with the cathode of the power supply. According to the device, the hydrogen isotope mixed gas can be rapidly separated, the separation factor of the gaseous hydrogen isotope is high, and the separation effect is good.

The invention relates to a deuterium water conversion and purification system, and belongs to the technical field of isotope separation and purification. The system comprises a deuterium gas supply unit, a deuterium gas electrochemical reaction conversion unit, a multi-stage condensation separation purification unit and a deuterium water storage unit. On the basis of deuterium gas supply pressure, non-stop automatic switching is triggered, and deuterium gas non-backflow control is executed through a backflow blocking mechanism; generating electric energy and tail gas containing deuterium water vapor based on continuously supplied deuterium gas and a drying oxidant; a gradient gas-liquid separation process and a closed-loop temperature control regulation mechanism are adopted to obtain primarily purified liquid deuterium water, and high-purity deuterium water is generated through a high-selectivity ion exchange adsorption process; and obtaining deuterium water storage capacity data and conductivity parameters, analyzing the deuterium water storage capacity data and the conductivity parameters with a preset conductivity parameter threshold value, and triggering purification material regeneration reminding. The system realizes collaborative linkage of deuterium gas supply, conversion, purification and storage monitoring, and ensures the continuity and purity stability of deuterium water preparation.

The present application particularly relates to a method for producing helium-3 from heavy water in a heavy water reactor, comprising: step 1, subjecting the heavy water in a moderator system of a heavy water reactor unit to negative pressure rectification to obtain concentrated high-tritium heavy water; step 2, subjecting the concentrated high-tritium heavy water in step 1 to beta decay to produce helium-3 raw gas; and step 3, subjecting the helium-3 raw gas in step 2 to active carbon adsorption, helium-argon separation and hydrogen isotope gas adsorption to obtain helium-3. The method for producing helium-3 from heavy water in a heavy water reactor avoids technical difficulties and high costs of helium-3 / helium-4 isotope separation, and has high technical maturity and good economy.

The invention discloses a device suitable for isotope separation and a sealing structure thereof, and relates to the field of isotope separation.The device comprises a supporting table and an ion acceleration pipeline fixedly installed at the top end of the supporting table, one end of the ion acceleration pipeline is communicated with an ion source, and the outer side of the ion acceleration pipeline is sleeved with a spiral cooling pipe in the length direction; one end of the spiral cooling pipe is connected with a pump body, the pump body is connected with a heat exchange pipe, and a cooling circulation system composed of the spiral cooling pipe, the pump body, the heat exchange pipe and the cooling water tank can rapidly take away heat generated during operation of the ion acceleration pipeline, the heat dissipation efficiency is higher, and when the first moving seat and the second moving seat move in the length direction of the spiral cooling pipe, the heat dissipation efficiency is higher. Wind power generated by the fan is evenly blown to the ion acceleration pipeline and the spiral cooling pipe through the exhaust port, auxiliary cooling of the ion acceleration pipeline is achieved, and meanwhile it can be prevented that condensate water is generated on the surface of the spiral cooling pipe due to too low temperature.

This invention belongs to the field of isotope separation technology, specifically relating to a self-evacuating valve. The invention includes a valve stem, valve body, sealing element, cavity, sealing port, air inlet, and self-evacuating gauge. The valve body has a through hole in its center. The valve stem is mounted at the top of the through hole. A sealing element is installed below the valve stem and on the inner wall of the through hole. The lower part of the sealing element forms a cavity, and the bottom of the cavity has a sealing port. The air inlet is located below the sealing port. A horizontal through hole is formed on the side wall of the valve body, and a self-evacuating gauge is installed at the top of the through hole. This invention has functions such as shut-off and self-evacuation, and can be directly used for self-evacuation of pipeline valves.

The invention provides a mounting method of a deep well rectifying tower for isotope separation, and belongs to the technical field of mounting of deep well rectifying towers. The installation method of the deep well rectifying tower for isotope separation comprises the following steps that a tower section is welded to the top of a reboiler section, after welding is finished, first quality detection is conducted on a first welding area between the reboiler section and the tower section, and flaw detection treatment comprises the steps that liquid nitrogen pouring treatment and 100% ray detection treatment are sequentially conducted on the first welding area; if the quality of the first welding area reaches a first preset standard, continuously welding a condenser section at the top of the tower section; if the quality of the first welding area does not reach the first preset standard, the first welding area is overhauled till the quality of the first welding area reaches the first preset standard, and then the condenser section continues to be welded to the top of the tower section. The long-term use at low temperature can be realized.

This invention discloses an isotope separation and enrichment device with a multipole mass analyzer, comprising a pre-chamber and a vacuum chamber, and a vacuum interface between the two. An ICP ion source assembly is installed inside the pre-chamber, and the ICP ion source assembly is connected to an ion extraction system inside the vacuum chamber via the vacuum interface. The multipole mass analyzer is connected to the rear side of the ion extraction system, followed by a pluggable receiver and a signal amplifier. The isotope separation and enrichment device also includes an electronic control system. This invention can improve the ionization efficiency of existing technologies, reduce device construction costs, and reduce maintenance difficulty.

This invention discloses an isotope separation and enrichment method using a multipole mass analyzer, comprising: injecting a high-concentration solution into a first chamber; ionizing the high-concentration solution in the first chamber using an ICP ion source assembly to form plasma; the plasma vacuum chamber formed in the first chamber then enters an ion extraction system; the extracted ions are introduced into a subsequent multipole mass analyzer; adjusting the voltage applied to the multipole mass analyzer according to the different elements in the sample to be enriched, so that a specific isotope to be separated passes through the multipole mass analyzer and enters a subsequent receiver; this invention can improve the ionization efficiency of existing technologies, reduce the construction cost of the device, and reduce the difficulty of maintenance.

The present invention relates to a carbon isotope separation device using an electron beam heating method. And a carbon isotope separation method using the carbon isotope separation device. Specifically, the carbon isotope separation apparatus according to one aspect comprises: a high vacuum electron beam chamber; a magnetic metal cylinder disposed in the high vacuum electron beam chamber and including a carbon mixture storage unit on an upper surface thereof; and a water-cooled sample holder in contact with the lower surface of the magnetic metal cylinder, and the carbon isotope separation device can efficiently separate and concentrate carbon isotopes.

The present application belongs to the technical field of uranium isotope separation process control, and particularly relates to a first alarm highlighting method for a unit fault state, which comprises the following steps: step one, defining a highlighted alarm variable; step two, designing and defining a reset control function; step three, establishing a control program flow; step four, designing and defining a first alarm variable highlighting display interface; and step five, configuration programming and commissioning. In the method, an operation personnel can quickly and accurately determine the fault of the unit by using the first alarm variable event information, and timely eliminate the fault, and the application effect is good.

This invention provides a hydrogen isotope separation system that can simplify the configuration of the heat transfer medium circuit. [Solution] The hydrogen isotope separation system 10 comprises an anode-side humidifier 14A, a separator 15, a coupler 17, a heat transfer medium circuit 30, and a control device 40. The heat transfer medium circuit 30 comprises a first flow passage 30A, a second flow passage 30B, a three-way valve 33, and a first temperature sensor 38A. The first flow passage 30A circulates the heat transfer medium to the coupler 17. The second flow passage 30B circulates the heat transfer medium to the anode-side humidifier 14A and the separator 15. The three-way valve 33 switches between connecting and disconnecting the first flow passage 30A and the second flow passage 30B. The first temperature sensor 38A detects the temperature of the heat transfer medium discharged from the coupler 17. The control device 40 connects the first flow passage 30A and the second flow passage 30B using the three-way valve 33 when the temperature T1 detected by the first temperature sensor 38A is above a predetermined temperature.

A split collection crucible assembly that includes a collection crucible and a collection cooling plate comprising a first plate portion removably coupled to a second plate portion, wherein when the first plate portion and the second plate portion are in an engaged position, a crucible slot is formed between the first plate portion and the second plate portion and the collection crucible is positionable in the crucible slot.

The invention relates to a germanium isotope separation method, device and system. According to the germanium isotope separation method, device and / or system, the problems that in the prior art, a germanium isotope separation method is small in scale, low in production efficiency, incapable of achieving continuous production, not suitable for industrial application and the like are solved through a chemical exchange method.

The invention belongs to the technical field of powder material preparation, and particularly relates to a method for synthesizing carbon-silicon and carbon-boron powder by using a carbon source. The heavy component mixture generated in the boron isotope separation process through a chemical exchange method is used as a novel carbon source, the problems that a traditional carbon source is high in cost and complex in technology are solved by optimizing the raw material ratio, the calcination technology and post-treatment parameters, industrial waste resource utilization is achieved, and meanwhile powder with the excellent structure and performance is prepared. The boron isotope separation heavy component mixture is used as a carbon source for the first time, waste is turned into wealth, the cost is reduced, industrial waste discharge is reduced, and the method conforms to the green chemistry concept. The invention provides an efficient, environment-friendly and controllable carbon silicon / carbon boron powder synthesis method through raw material innovation and process optimization, and has remarkable economic value and technical advantages.

The invention relates to the technical field of isotope separation and special water treatment, and discloses a vacuum distillation preparation method of low-deuterium and low-tritium water, which comprises the following steps: 1, raw material pretreatment: carrying out sand filtration, activated carbon filtration and ultrafiltration treatment on raw material water to obtain pretreated water; the pretreated water, concentrated sulfuric acid and copper sulfate pentahydrate are mixed according to the mass ratio of 100: (5-15): (0.2-1.0), cooling is conducted in an ice-water bath till the temperature does not exceed 40 DEG C, and uniform stirring is conducted; and 3, low vacuum distillation: transferring the mixed system into a distillation device, adjusting the vacuum degree to 0.02-0.08 MPa, heating to 60-90 DEG C, controlling the distillation rate to be 10-20% of the volume of the raw material liquid per hour, and carrying out constant temperature distillation. The vacuum distillation preparation method of the low-deuterium and low-tritium water is low in energy consumption and low in cost, the low-vacuum-degree condition of 0.02-0.08 MPa is adopted, the distillation temperature is only 60-90 DEG C, and compared with a traditional high-vacuum and high-temperature distillation process, the energy consumption is reduced by 40% or above; meanwhile, complicated multi-stage rectification equipment is not needed, so that the equipment investment and the operation cost are obviously reduced.

The present invention discloses an active circulation type solution type reactor system, and relates to the technical field of nuclear reactor design, the active circulation type solution type reactor system comprises: a loop fuel circulation system, which is respectively connected with a fuel solution outlet and a fuel solution inlet of a reactor core through a loop pipeline; along the conveying direction of the primary loop pipeline, the primary loop fuel circulation system comprises a heat exchanger, a solid impurity filtering unit and a gas-water separation unit which are sequentially connected in series, and an isotope separation and radioactive waste disposal unit which is connected to the primary loop pipeline in parallel; the primary-loop fuel circulation system further comprises a fuel solution circulation unit. By adopting the scheme, the fuel solution flows in the circulating system, and a series of on-line operations such as fission, impurity removal and target isotope extraction of the fuel solution are respectively realized in each subsystem of the flowing path, so that the reactor system can continuously run on line, the economical efficiency can be improved, and the performance of the reactor can be improved.

This invention relates to a method for generating a high-purity Ac-225 radioactive beam based on an online isotope separator. A high-energy proton beam with an energy of 100 MeV is generated using a cyclotron accelerator. This high-energy proton beam is transmitted to an ISOL target chamber and bombards a thorium carbide target within the chamber, causing a nuclear reaction. Atoms produced in the nuclear reaction escape from the target and interact with a specific wavelength of incident laser light, resulting in stimulated ionization. The stimulated ionized radioactive nuclear beam is extracted by a high-voltage ion source and then transmitted via a beam transport system to a pre-analytical magnet. The radioactive nuclear beam undergoes preliminary separation by the pre-analytical magnet. After preliminary separation, the radioactive nuclear beam is further accelerated by a high-voltage accelerator tube and then further separated by the main analytical magnet to improve the purity of the beam. Compared with radiochemical separation methods, this invention offers higher separation efficiency and a shorter separation cycle, yielding Ac-225 with a purity exceeding 99%. Further purification is expected to meet the requirements of clinical trial standards.

The utility model belongs to the technical field of radioactive isotope separation and purification, and particularly relates to a system for separating and purifying carrier-free lutetium 177. Comprising a mounting rack, a salt transfer assembly arranged in the middle of the front side of the mounting rack, a valve assembly arranged in the middle of the rear side of the mounting rack, a separation and purification column arranged on one side of the salt transfer assembly, a sample injection system arranged on one side of the valve assembly, a fraction assembly arranged above the mounting rack and a waste liquid assembly arranged on one side of the mounting rack, the control terminal controls the sampling system and the on-off of valves in the valve assembly to control the flow of liquid in the separation and purification system, so that the functions of ytterbium and lutetium separation, lutetium-to-salt concentration and ytterbium-to-salt recovery in the separation and purification system are realized. The utility model solves the problems in the prior art that the whole system for separating and purifying the carrier-free lutetium-177 is large in size, large in occupied area, high in requirement on automation control degree and short in service life of parts.

The invention relates to the technical field of functional coating materials, and particularly discloses a method for strengthening hydrogen isotope resistance of a rare earth oxide coating based on defect engineering. The method comprises the following steps: preparing rare earth sol through a liquid phase reaction, coating the rare earth sol on a metal base material to form a wet film, preheating, and introducing high-concentration point defects into a rare earth oxide crystal structure in a high-temperature heat treatment stage by accurately regulating and controlling atmosphere oxygen partial pressure. The innovation of the invention lies in that the quantitative regulation and control relationship between the oxygen partial pressure and the defect concentration is established, and the defect is used as a trap center of hydrogen isotope diffusion, so that the hydrogen resistance of the coating is greatly improved. According to the method, the uncontrollability of defects introduced by traditional doping or irradiation is avoided, the hydrogen isotope permeability of the coating can be reduced by 2-3 orders of magnitude, and the coating is complete in structure, high in binding force and suitable for the advanced fields of nuclear fusion reactor first wall protection, hydrogen isotope separation membranes, hydrogen energy storage and transportation equipment and the like.

This invention belongs to the field of ion source outlet angle measurement technology, and specifically relates to a device for measuring the outlet angle of a stable isotope separator ion source. The device includes a blind plate, with a first probe assembly and a second probe assembly mounted on the side wall of the blind plate. The first probe assembly includes a first housing, with a drive motor mounted on the side of the first housing. The output shaft of the drive motor is connected to a ball screw, and a first slide is threaded onto the surface of the ball screw. A first bellows pressure block is mounted on the first slide. This invention, by setting up the first and second probe assemblies and with a simple overall mechanical structure, achieves lower production costs while meeting functional requirements. Furthermore, the vacuum transition from high to low vacuum is more stable, reducing maintenance frequency and better ensuring the production capacity of stable isotopes, thus better meeting market demand for stable isotopes.

A gas chromatograph and method for H2 isotope separation and detection, the gas chromatograph comprising: an electronic flow controller, a sample injection valve, a cutting valve, a first chromatographic column, a second chromatographic column, a third chromatographic column, a liquid nitrogen cold trap and a plasma emission detector, the input and output sides of the first chromatographic column are connected with the sample injection valve and the cutting valve respectively, the input and output sides of the second chromatographic column are connected with the cutting valve and the third chromatographic column respectively, the input and output sides of the third chromatographic column are connected with the second chromatographic column and the plasma emission detector respectively, the second chromatographic column and the third chromatographic column are placed in the liquid nitrogen cold trap and immersed below the liquid level of the liquid nitrogen, the first chromatographic column is a molecular sieve chromatographic column, the second chromatographic column and the third chromatographic column are chromatographic columns filled with Al2O3 filler, wherein the second chromatographic column and the third chromatographic column use γ-Al2O3 filler treated by soaking in saturated MnCl2 solution. Thus, hydrogen isotopes can be effectively separated.

This invention provides a hydrogen isotope separation system that can suppress the degradation of performance during startup. [Solution] The hydrogen isotope separation system 10 comprises a separator 15 having an ion exchange membrane 15a, an anode 15b, and a cathode 15c. The hydrogen isotope separation system 10 comprises an anode supply path 10a that supplies light hydrogen containing one or more hydrogen isotopes toward the anode 15b, and a cathode supply path 10b that supplies cathode gas toward the cathode 15c. The hydrogen isotope separation system 10 comprises a mass spectrometer 20 and a control device 40. The mass spectrometer 20 detects the isotope ratio related to the concentration of hydrogen isotopes in the gas supplied to the anode 15b of the separator 15 and the gas discharged from the anode 15b. The control device 40 increases the separation coefficient α when the supply-side concentration ratio, which is the concentration ratio of deuterium and tritium to light hydrogen on the supply side of the anode 15b, is less than or equal to a first predetermined value.

The present application belongs to the technical field of isotope separation, and particularly relates to a container storage device. The present application comprises a box, a cover plate, a collector, a collection tube, a collector plug, a fan, a water tank, a refrigeration sheet, a vacuum hose, an evacuation copper pipe, a micro pump, a touch screen, a PLC, and a buckle. The collector is provided with a collection tube at each end, and the other end of the collection tube is installed on the collector plug. The other ends of the two collector plugs are connected through the evacuation copper pipe, and the evacuation copper pipe is connected with the micro pump. The collector, the collection tube, and the collector plug are connected with the refrigeration sheet through the vacuum hose respectively. The fan and the water tank are installed in the box. The top of the box is connected with the cover plate through the buckle. The cover plate is provided with the PLC, and the PLC is provided with the touch screen. The present application can provide a sealed and refrigerated storage environment for the collector of the centrifugal factory, and avoid material leakage.

A fuel processing system for a magnetic confinement fusion device, such as a fusion power reactor, is provided. The processing system includes a plasma centrifuge differential pump having a single outlet. When connected to an output of the fusion containment device, such as via a divertor, the plasma centrifuge differential pump maintains a pressure within the fusion device, thus increasing the tritium burn efficiency. The plasma centrifuge differential pump also allow for separation and removal of helium and other materials from the plasma used by the fusion device.

The invention provides a separation system, and belongs to the technical field of isotope separation, and the separation system comprises a raw material preparation device, a separation device, a first collection device and a second collection device. The raw material preparation device comprises a first raw material container, a mixing reactor and a second raw material container, the mixing reactor is used for receiving mixed gas and reacting to generate substances containing at least two isotopes in the mixed gas, and the second raw material container is connected with the mixing reactor to receive gas discharged after reaction in the mixing reactor. The separating device is used for receiving gas in the first raw material container or the second raw material container and separating the received gas, the first collecting device is connected with the separating device to receive product gas separated by the separating device, and the second collecting device is connected with the separating device to receive tail gas separated by the separating device. By judging whether the mixed gas received by the separation system passes through the mixing reactor or not, the composition of the mixed gas required by separation can be flexibly obtained according to actual requirements.

This invention provides a hydrogen isotope separation system that can suppress the decline in performance during shutdown. [Solution] The hydrogen isotope separation system 10 includes a separator 15 having an ion exchange membrane 15a, an anode 15b, and a cathode 15c. The hydrogen isotope separation system 10 includes an anode supply path 10a that supplies light hydrogen containing at least one type of hydrogen isotope toward the anode 15b, and a cathode supply path 10b that supplies cathode gas toward the cathode 15c. The hydrogen isotope separation system 10 includes an electrolytic unit 12 provided in the anode supply path 10a, condensers 16A and 16B provided on the discharge side of the separator 15, a second heat transfer medium circuit 40 that supplies a refrigerant to each condenser 16A and 16B, and a control device 50. The control device 50 stops the cooling of each condenser 16A and 16B by the second heat transfer medium circuit 40 after the electrolytic unit 12 and separator 15 are stopped during the system shutdown process.

The invention belongs to the technical field of electrochemical separation materials, and particularly discloses a zeta-V2O5 material with a tunnel structure as well as a preparation method and application of the zeta-V2O5 material. According to the invention, alpha-V2O5 and silver salt are used as precursors, and zeta-V2O5 with a one-dimensional tunnel structure is successfully constructed through a two-step hydrothermal method. The preparation method is simple, the raw materials are easy to obtain, the reaction conditions are mild, the crystal structure of the product is stable, the purity is high, and the problem that pure-phase zeta-V2O5 is difficult to obtain through a traditional method is solved. The prepared zeta-V2O5 has specific interstitial sites and shows excellent selective insertion capacity for lithium ions, the problems that a traditional lithium isotope separation process is high in energy consumption, large in pollution and the like are solved through a method for efficiently separating Li isotopes through a mixed capacitive deionization technology, and a new way is provided for obtaining nuclear fusion fuel 6Li in a green and low-carbon mode.