103 results about "Isotope separation" patented technology

The invention discloses a method for preparing deuterium-depleted water through cooperation of magnetic resonance and electrolysis strengthening, and particularly relates to the technical field of deuterium-depleted water preparation, and the method comprises the following steps: S1, injecting water to be treated into a magnetic resonance reaction chamber, and carrying out magnetic resonance treatment, so that the vibration energy level of a deuterium-oxygen bond is improved through a nuclear magnetic resonance effect, the bond energy is enhanced to 5.0-5.2 eV, and the deuterium-depleted water is obtained; forming a metastable-state deuterium-containing water molecular structure; s2, the water subjected to magnetic resonance treatment is guided into a three-electrode electrolytic bath for pre-electrolysis, then a gradient voltage electrolysis process is adopted for reinforced electrolysis to form a deuterium concentration gradient, and therefore hydrogen and electrolytic residual liquid are separated; and S3, finally performing gas-liquid isotope fractionation to finally prepare the deuterium-depleted water. According to the method, deuterium-oxygen bond energy is enhanced through magnetic resonance pretreatment, low-temperature gradient electrolysis and vacuum rectification are combined, a magnetoelectric synergistic isotope separation system is constructed, and the method has the advantages that the separation efficiency can be improved, the energy consumption can be reduced, the separation coefficient can be improved, the material utilization rate can be improved, and the deuterium content of the prepared deuterium-depleted water is lower than 30 ppm.

The invention relates to the technical field of isotope separation, and particularly discloses a functionalized ionic liquid as well as a preparation method and application thereof in separation of boron isotopes. The ionic liquid prepared from halogenated ether, a nitrogen-containing compound and fluorine-containing inorganic salt is used as a complexing agent for boron isotope separation. The ionic liquid has good chemical stability and thermal stability and can be kept stable in the long-time separation process of boron isotopes; the ionic liquid has unique selectivity, has different affinity and complexing stability to 10B and 11B, and is convenient to realize accurate separation of 10B and 11B; the boron isotope separation agent also has excellent solubility and flowability, can fully contact and react with boron isotopes, improves the separation efficiency, reduces equipment blockage and energy consumption, and provides convenient conditions for large-scale industrial boron isotope separation; in addition, the ionic liquid has better environmental friendliness, better meets the development requirements of green chemistry, and has huge application potential in the field of boron isotope separation.

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 invention provides an isotope separation system and an isotope separation method.The isotope separation system comprises a cryogenic temperature and pressure swing adsorption device, the cryogenic temperature and pressure swing adsorption device comprises at least two adsorber units, each adsorber unit comprises a liquid nitrogen container and an adsorber, and in each adsorber unit, the liquid nitrogen container is communicated with the adsorber; the adsorber is soaked in the liquid nitrogen in the liquid nitrogen container; the adsorber comprises a pipe wall, the material of the pipe wall comprises a first material, the constant volume heat capacity Qvh of the unit length of the pipe wall is larger than a first preset value, and the wall thickness D of the pipe wall is 0.5-8 cm; a modified Nusselt criterion # imgabs0 # related to the material and thickness of the tube wall is controlled to be within a predetermined range. The problems of low isotope separation efficiency, poor regeneration effect, high liquid nitrogen consumption and high energy consumption in the prior art are solved, and the cyclic utilization rate of the adsorbent and the heavy component isotope recovery rate are remarkably increased.

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 application relates to the technical field of isotope separation, in particular to a SiO2@CeO2 core-shell material with silica supported cerium dioxide, a preparation method thereof and application of the SiO2@CeO2 core-shell material in Ge / Ga separation. 68 Efficient adsorption of Ge and 68 Effective elution of Ga; the SiO2@CeO2 core-shell material is used as a stationary phase, hydrochloric acid is used as a mobile phase, Ge / Ga is efficiently separated based on solid-phase extraction, and therefore the SiO2@CeO2 core-shell material can be used as 68 Ge- 68 Ga generator column packing.

This application relates to a composite catalytic material, a preparation method thereof, an electrode, its application, and a reactor for electrocatalytic hydrogen isotope separation. The composite catalytic material comprises a substrate, a nickel metal organic framework material layer, ruthenium particles, and a graphene layer. The nickel metal organic framework material layer is disposed on the surface of the substrate, the graphene layer is disposed on the surface of the nickel metal organic framework material layer away from the substrate, and the ruthenium particles are disposed between the nickel metal organic framework material layer and the graphene layer. This composite catalytic material is fabricated into an electrode for electrocatalytic hydrogen isotope separation, effectively regulating the diffusion rate of hydrogen and deuterium in a solution, thereby improving the efficiency of hydrogen-deuterium separation.

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 provides a preparation method of a spin-free autonuclear isotope and a quantum bit structure. The preparation method comprises the following steps: providing a substrate; according to the embodiment of the invention, the surface area of the substrate is marked in a partitioned manner to obtain the plurality of first sub-areas, so that the nuclear-free spin isotope can be conveniently and accurately positioned subsequently through the smaller first sub-areas. And performing isotope separation and purification on the elements in each first sub-region through laser to obtain second sub-regions corresponding to each first sub-region, and determining distribution information of the nuclear-free spin isotopes in each second sub-region, the distribution information being used for identifying regions where the nuclear-free spin isotopes are located in the second sub-regions. In a word, low-cost preparation can be achieved due to the fact that a centrifugal machine is not needed when the nuclear-free spin isotope is prepared in the mode, and on the other hand, the specific area where the nuclear-free spin isotope is located can be accurately positioned by conducting positioning marking on the surface area of the substrate, and accurate positioning of the nuclear-free spin isotope is achieved.

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 application relates to a liquid-phase electric quadrupole device for isotope separation, which comprises a sample injection unit for raw liquid injection, a separation unit for isotope separation, a recovery liquid collection unit for collecting liquid after separation and a power supply (1) for providing electric energy; the separation unit is connected with the sample injection unit, the power supply and the recovery liquid collection unit respectively. Compared with the prior art, the application has the advantages of small floor area, low energy consumption and great economic cost saving; moreover, the device has the advantages of simple structure, simple operation, direct injection for separation and effective reduction of experimental cost.

The invention provides a helium isotope low-temperature rectification device and a helium isotope separation method, and the helium isotope low-temperature rectification device comprises a rectification tower which is a packed tower; the condensing unit is arranged at the top of the rectifying tower, is communicated with the rectifying tower and is used for condensing the rising gas phase into a liquid phase; the reboiling unit is arranged at the bottom of the rectifying tower, is communicated with the rectifying tower and is used for heating a liquid phase to generate a rising gas phase; a liquid flow guide part is arranged in a communication area of the condensing unit and the rectifying tower and is used for guiding flow of reflux liquid; a gas flow guide part is arranged in a communication area of the reboiling unit and the rectifying tower and is used for guiding flow of a rising gas phase. By optimizing the design and operation conditions of the low-temperature rectification device, high-efficiency, continuous and large-treatment-capacity helium-3 extraction can be realized.

The invention relates to the technical field of isotope separation, and provides a helium-3 enrichment device which comprises a separation loop and a refrigeration loop, the separation loop comprises a raw material tank, an ultra-leakage assembly, a gas inlet pipeline, a first liquid outlet pipeline and a second liquid outlet pipeline, the raw material tank is provided with a first inner cavity and a first outer cavity, and the gas inlet pipeline and the first liquid outlet pipeline are connected with the first inner cavity; the second liquid outlet pipeline is connected with the first inner cavity through the leakage exceeding assembly, and the gas inlet pipeline is connected with a mixed gas source. The refrigerating circuit comprises a liquefying tank, a first pressure reducing assembly and a refrigerating machine, the liquefying tank is connected with a helium-4 gas source, the refrigerating machine refrigerates the liquefying tank, the liquefying tank is connected to the first outer cavity, and the first pressure reducing assembly reduces the pressure of the first outer cavity. According to the arrangement, by cooling the raw material tank, helium-4 in the mixed gas is changed into superfluid capable of passing through the super-leakage assembly, helium-3 in the mixed gas is still normal liquid which cannot pass through the super-leakage assembly, so that crude separation of helium-3 and helium-4 is realized, and helium-3 concentration of the raw material gas is improved.

The invention belongs to the technical field of hydrogen and isotope separation, and particularly relates to a hydrogen and hydrogen isotope enriching and liquefying system. Comprising three stages of cooling and liquefying units connected in series and an isotope enrichment system, the first-stage cooling unit comprises a first-stage ortho-parahydrogen converter and a first-stage liquefying cooler, and a high-pressure expansion machine is configured; the second-stage cooling unit comprises a second-stage ortho-parahydrogen converter and a second-stage liquefaction cooler, and is provided with a medium-pressure expansion machine; the third-stage cooling unit comprises a third-stage ortho-parahydrogen converter and a third-stage liquefaction cooler, and is provided with a low-pressure expansion machine; the isotope enrichment system comprises a three-stage isotope enrichment device, an isotope enrichment tank and a liquid hydrogen tank which are connected in series, and a closed loop is formed by a liquid hydrogen expansion valve and a three-stage liquefaction cooler. According to the invention, parahydrogen after passing through each stage of ortho-parahydrogen converter cannot be converted into ortho-hydrogen again due to temperature rise, and low-temperature cold hydrogen generated by isentropic expansion of the high-pressure turbo expander absorbs heat generated by conversion of ortho-hydrogen into parahydrogen of product hydrogen after hydrogen refrigeration after ortho-parahydrogen conversion.

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.

The application provides a helium isotope low-temperature adsorption separation system and method, and relates to the technical field of isotope separation. The helium isotope low-temperature adsorption separation system comprises an adsorption column, a low-temperature control unit, an adsorbent regeneration unit, a helium isotope gas outlet control unit, a helium isotope gas inlet and recovery control unit and a system purging unit, and the low-temperature control unit comprises a refrigerator, a vacuum cover, a first-stage cold screen, a second-stage cold screen, a first-stage anti-radiation screen, a second-stage anti-radiation screen, an inlet pipe and an outlet pipe. The first-stage anti-radiation screen is arranged in the interior of the vacuum cover, the first-stage cold screen is arranged at the opening of the first-stage anti-radiation screen, and the first-stage cold screen is provided with a mounting hole. The helium isotope low-temperature adsorption separation system has the characteristics of precise temperature control in a wide temperature range, precise adsorption pressure control, fast rewarming desorption speed, high adsorption efficiency, gas recyclability, simple structure and convenient operation, and has great significance for the separation research of helium isotopes.

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 discloses a carbon isotope separation device and a starting method, and relates to the technical field of carbon isotope separation. The starting method of the carbon isotope separation device comprises the following steps: starting three rectifying towers in the carbon isotope separation device; introducing a CO raw material into a tower from a middle feeding pipeline of the first-stage rectifying tower and a middle feeding pipeline of the second-stage rectifying tower respectively; starting a first-stage rectifying tower and a second-stage rectifying tower until the first-stage rectifying tower and the second-stage rectifying tower respectively enter a concentration and enrichment balance state; and in the process of waiting for the second-stage rectifying tower to enter a concentration and enrichment equilibrium state, introducing a CO raw material from a tower bottom feeding pipeline of the third-stage rectifying tower to charge the tower, starting the third-stage rectifying tower, and rectifying to obtain a 12C isotope product. According to the starting method of the carbon isotope separation device, in the process of waiting for the second-stage rectifying tower to enter the concentration and enrichment balance state, the high-purity carbon-12 product is produced, and resource waste is reduced.

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.

The utility model provides a helium-3 and helium-4 co-production system, and relates to the field of isotope separation. The helium-3 and helium-4 co-production system comprises a helium-4 liquefying device, a helium-3 enriching device and a helium-3 purifying device; the helium-4 liquefying device is used for liquefying helium to form liquid helium; the helium-3 enriching device is communicated with the helium-4 liquefying device, and the helium-3 enriching device is used for increasing the concentration of helium-3 in liquid helium; the helium-3 purification device is communicated with the helium-3 enrichment device and the helium-4 liquefaction device, and the helium-3 purification device is used for purifying helium-3. According to the helium-3 and helium-4 co-production system provided by the utility model, helium-3 is continuously purified on the basis of helium extraction, so that helium-3 can be extracted on a large scale at lower cost. The main economic cost of the process is at the front end, namely the helium extraction part and the helium liquefaction part in the helium-rich natural gas, the cost of a helium-3 enrichment and helium-3 purification device is low, and the helium-3 extraction cost is greatly reduced on the whole.

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.

This invention relates to a dual-column cyclic preparation method. 239 The apparatus and method for Np tracers belong to the field of actinide isotope separation and preparation technology, and solve the problem of... 239 The technical challenges of low purity and unstable recovery rates in Np tracer preparation are addressed by this device, which includes a temperature controller, a radiation shield, a storage tank unit, a chromatography separation unit, a waste liquid collector, a product collector, valves, and a transfer pump. Liquid from the storage tank unit is pumped into the chromatography separation unit, and liquid exiting the chromatography separation unit enters either the waste liquid collector or the product collector. The chromatography separation unit includes a TODGA chromatography adsorption column and LN or P... 204 or P 507 Chromatographic adsorption column. The method includes preparing a feed solution, washing solution, eluent, and chromatographic adsorption column before separation; adsorption, washing, and elution steps for neptunium. This invention is used for preparing... 239 Np tracer.

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.

The invention belongs to the technical field of isotope separation, and particularly relates to a method for separating Th / Ac based on activated carbon column chromatography, which comprises the following steps: based on column chromatography, taking activated carbon as a stationary phase, and realizing Th / Ac separation by controlling the pH value of a mobile phase; the activated carbon is functional activated carbon rich in hydroxyl and carboxyl functional groups and prepared by heating and oxidizing coconut shell activated carbon through nitric acid; when the pH value of the mobile phase is greater than or equal to 2, the functional activated carbon adsorbs Th and Ac; and when the pH value of the mobile phase is reduced to 1, the functional activated carbon only adsorbs Th and does not adsorb Ac. The activated carbon disclosed by the invention has the characteristics of good radiation resistance, low price and simplicity in preparation, the separation process of the 225Ac is simple, automatic and large-scale production is easy to realize, the radioactive waste is less, and the recovery rate and the purity of the 225Ac are high.

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.