383results about "Isotope separation" patented technology

The invention discloses a method for continuously and efficiently adsorbing and separating hydrogen isotopes. The hydrogen isotopes are separated by adopting a multi-tower variable-temperature variable-pressure device operated in a simulated moving bed operation mode. When the device runs, each adsorption tower needs to sequentially execute the following steps: 1, adsorption; 2, replacement; 3, heating; 4, vacuumizing and desorbing; 5, carrying out vacuum purging; 6, pressurizing and cooling; the operation mode of the simulated moving bed is that an adsorption tower is frequently, sequentially and synchronously moved along the gas flowing direction in the tower through all gas input and output ports, so that an adsorbent phase and a gas flowing phase in the tower form countercurrent flow, and the hydrogen isotope adsorption separation efficiency is enhanced. The invention relates to a technological process of cyclic adsorption, replacement, heating, vacuum desorption, pressurization and cooling, continuous and efficient hydrogen and isotope adsorption separation is realized, multi-tower serial adsorption and replacement are adopted in the process, and separation of hydrogen isotopes (such as H2 / D2) is enhanced; and the desorption efficiency of heavy components is improved by adopting a heating and vacuumizing depressurization coupling mode.

The invention discloses a preparation method and application of a membrane separation material based on external field enhanced water isotope separation. The preparation method comprises the following steps: firstly, pre-enriching a precursor component containing a polymerizable monomer, a cross-linking agent and a photoinitiator in a confinement pore channel of a nano-porous carrier through an impregnation-encapsulation strategy; and then, through in-situ photo-initiation polymerization, a covalent cross-linked functional polymer network is constructed in the pore channel, and stable packaging of the polymer is realized. In the water isotope separation period, external field conditions are regulated and controlled, the molecular conformation of a polymer chain is accurately controlled, and the separation performance is optimized. According to the invention, by virtue of an external field strengthening technology, the intramolecular / intermolecular interaction is destroyed, and the macromolecular chain is converted from contraction to stretching, so that more functional sites are exposed, and the water isotope separation material designed by the invention has a huge practical application prospect.

The invention belongs to the technical field of deuterium water treatment, and particularly relates to a preparation method and system of deuterium-depleted water, which is based on combination of an MVR-EDI-air pump and realizes functions through a three-level architecture of pretreatment, gradient separation and deuterium recovery. Comprising a raw water input module, an EDI pure water pretreatment module, a multi-stage MVR evaporation module, a medical water integration module and a deuterium water concentration treatment module, and the raw water input module, the EDI pure water pretreatment module, a primary treatment module, secondary to N-stage treatment modules and the deuterium water concentration treatment module are connected into a whole. By combining filtering purification, low-temperature distillation and a power air energy pump, the production cost is greatly reduced, the deuterium content can be lower than 50 or 30 PPM and further can be lower than 5 PPM, and the water is suitable for medical treatment, aerospace and high-end laboratories; the multi-gradient low-deuterium water production enables deuterium resources to be recycled, and is high in production efficiency, free of wastewater discharge, low in energy consumption and energy-saving.

The invention discloses a dry reboiler for an isotope rectifying tower device. The dry reboiler comprises a porous thin-wall structure and a heating supporting part, wherein the heating supporting part comprises a liquid collecting surface, the porous thin-wall structure is connected with the heating supporting part and located above the liquid collecting surface of the heating supporting part, and the porous thin-wall structure is configured to provide a capillary surface for liquid to flow; liquid on the liquid collecting surface is sucked into the thin wall of the porous thin-wall structure from bottom to top through capillary force, so that gas and liquid flowing in the porous thin-wall structure are subjected to heat and mass transfer; the heating supporting part is provided with a heating rod, the heating supporting part is further configured to transfer heat to the liquid collecting surface of the heating supporting part and the porous thin-wall structure through the heating rod, and the dry type reboiler can reduce the liquid holdup and has the functions of quickly responding to load change, being compact in structure and the like, so that the production requirements of high efficiency, energy conservation and stability are met.

The invention relates to a separation method suitable for At-211 produced by a linear accelerator, which comprises the following steps: performing gradient pressing on bismuth powder and a pore forming agent, and sintering on a porous silicon carbide substrate to form a gradient pore bismuth-silicon carbide composite target material; bombarding the gradient pore bismuth-silicon carbide composite target material through a high-energy particle beam generated by a linear accelerator, and carrying out nuclear reaction on bismuth atoms in the target material to generate At-211; the bombarded target material is pretreated through argon plasma; distilling the pretreated target material under pulse carrier gas to realize volatilization separation of At-211, wherein the carrier gas comprises inert gas, reducing gas and organic acid steam; the distilled gas is subjected to gradient condensation through the micro-channel condenser; and adding an extracting agent into the micro-channel condenser, and dissolving the At-211 in the extracting agent to obtain an At-211 solution. The high-flux separation method of At-211 suitable for linear accelerator production, provided by the invention, is stable, efficient and rapid.

The invention relates to the technical field of hydrogen purification, and discloses a palladium membrane and a preparation method thereof.The method comprises the steps that irradiation treatment is conducted on a palladium-based membrane to obtain the palladium membrane, irradiation ions are adopted to conduct irradiation on at least one surface of the palladium-based membrane in the irradiation treatment, the ion implantation dosage is 1 * 10 < 17 > ions / cm < 2 >-8 * 10 < 17 > ions / cm < 2 >, and the energy of the irradiation ions is 15 keV-2 MeV. The palladium membrane provided by the invention has the advantages of high permeation flux, excellent isotope separation effect, short activation time and stable long-term operation stability.

The invention relates to the technical field of metal organic framework materials (MOF) and isotope separation, in particular to a functionalized metal organic framework material for water / heavy water separation and a preparation method and application thereof. The metal organic framework material is a porous crystal material which is formed by coordination self-assembly of metal ions and V-shaped organic ligands and has a periodic network structure; the V-shaped organic ligand is a V-shaped dicarboxylic acid organic ligand modified by an oxygen-containing functional group designed through topological functionalization. According to the metal organic framework material, through topological functional design of a V-shaped organic ligand, a space confinement channel and a high-density oxygen active site are integrated in the same MOF material, and an ideal model system is provided for identification of water isotopes; according to the metal organic framework material, the framework structure flexibility, the pore channel confinement effect and the molecular recognition capability can be synergistically regulated and controlled, so that efficient recognition and separation of water / heavy water are realized.

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.

An isotope ratio spectrometer is operated for measurement of a sample. First isotope ratios and first signal intensities are measured for a reference in the spectrometer, over a first measurement time period. A first relationship comprising a relationship between the first isotope ratios and the first signal intensities is determined. Sample isotope ratios and sample signal intensities are measured in the spectrometer, over a second measurement time period subsequent to the first measurement time period. Second isotope ratios and second signal intensities for a reference are measured in the spectrometer, over a third measurement time period subsequent to the second measurement time period. A second relationship comprising a relationship between the second isotope ratios and the second signal intensities is determined. A reference isotope ratio is estimated for a time X within the second measurement time period, based on the first relationship and the second relationship.

The invention discloses a process and a control method for continuous separation of hydrogen isotopes, and belongs to the technical field of hydrogen isotope separation. According to the process, a countercurrent continuous operation mode is adopted, an adsorption tower is divided into an adsorption area, a replacement area and a regeneration area, and reverse movement of an adsorbent and a material is simulated by periodically switching the material inlet and outlet positions of the adsorption tower; the adsorption towers and connecting pipelines are soaked in a constant-temperature coolant, and separation is realized by virtue of acting force difference of an adsorbent on hydrogen isotopes; according to the control method, digital control logic is adopted, the valve state is edited through a spreadsheet, software is controlled to analyze data, a PLC executes valve switching, and accurate regulation and control of the multi-tower operation state under different working conditions are achieved. The method provided by the invention solves the problems of high equipment investment and large energy consumption of a traditional separation method, has the advantages of high separation factor, high recovery rate and stable continuous operation, and is suitable for hydrogen isotope separation requirements of different feed gas proportions and different treatment capacities.

The invention belongs to the technical field of radioactive metal isotope ion chromatographic separation, and discloses a medical radioactive isotope purification multichannel ion liquid chromatography system. The system comprises an automatic sample injection system, a parallel sampling and leaching channel, a parallel multi-column chromatographic structure, an online radiation dose monitoring module, a multi-channel tail end detection system, a recycling structure and a central control system. By adopting a full-automatic sample injection and multi-channel parallel chromatography structure, parallel separation, real-time radiation monitoring, multi-mode online detection and closed-loop recovery are realized, and the problems of insufficient nuclear purity, low separation efficiency, low target recovery rate and high radiation exposure of a traditional method are solved.

The application belongs to the technical field of graphene composite membrane preparation, and specifically discloses a preparation method and application of a Nafion / graphene / PES-liquid Nafion semi-hydrated composite membrane, wherein the preparation method comprises the following steps: attaching copper foil with graphene to a solid Nafion membrane, with the side of the copper foil with better graphene growth quality being in contact with the solid Nafion membrane; performing heat pressing treatment on the device; etching off the graphene on the other side of the copper foil that is not in contact with the Nafion membrane by using a dry etching method; removing the copper foil by using a wet etching method; drying the Nafion / graphene composite membrane at room temperature; immersing a PES porous membrane in liquid Nafion to obtain a PES-liquid Nafion sample; placing the sample in a water vapor environment to perform a semi-hydrated reaction and obtain a PES-liquid Nafion semi-hydrated membrane; and after drying at room temperature, attaching the Nafion / graphene composite membrane to the PES-liquid Nafion semi-hydrated membrane to obtain a Nafion / graphene / PES-liquid Nafion semi-hydrated composite membrane. The semi-hydrated composite membrane prepared by the application can be stably electrolyzed in liquid water for a long time, can enrich heavy water, and can better protect the graphene.

The present application relates to a kind of tritium separation method of tritium-containing wastewater and its reactor system, application, the tritium separation method of tritium-containing wastewater of the present application is ultraviolet irradiation promotes separation method, comprising: step 1) tritium-containing wastewater is introduced into the reaction containment of reactor system and is contacted with adsorption material to form liquid-solid two-phase contact system, step 2) after ultraviolet light is irradiated to liquid-solid two-phase contact system, make tritium enrich in adsorption material;Step 3) after the liquid-solid two-phase contact system of irradiation is completed, solid-liquid separation is obtained to low concentration tritium treatment water and tritium-rich adsorption material.The method of the present application is irradiated by ultraviolet light, accelerates hydrogen / tritium isotope exchange and adsorption process, can obtain higher tritium removal rate and adsorption amount under the same processing time.The present application belongs to energy-saving and environmental protection industry, especially in wastewater environmental control and nuclear pollution wastewater treatment in the environmental protection application of the recovery treatment of nuclear radioactive pollution elements plays a key role.

The invention discloses a lithium isotope enrichment and separation system and a separation method. The enrichment and separation system comprises an oleophobic lithium salt water solution serving as a water phase and an extraction organic phase; wherein the lipophobic lithium salt aqueous solution comprises lithium salt and water which are insoluble in the organic phase, and the extraction organic phase comprises a diluent, lipophilic and / or amphiphilic lithium salt and a chelating agent. According to the separation method provided by the invention, under the condition that the controllable lithium ion distribution ratio is obtained, the two-phase isotope balance time is shortened, the stability and the phase separation efficiency of the system are greatly improved, and the content of organic matters in the extracted waste liquid is reduced.

The invention relates to the technical field of neon isotope separation, and discloses a neon isotope separation system and method.The neon isotope separation system comprises a neon gas tank, a supercharger, a first-stage heat exchanger, a second-stage heat exchanger, a mixing refrigerator and a multi-stage rectifying tower, and cold neon discharged from the top of the rectifying tower except the first-stage rectifying tower is subjected to heat exchange through the second-stage heat exchanger and the first-stage heat exchanger and then flows back to the supercharger, and the cold neon is effectively used as a refrigerant to cool neon. And then part of neon cooled by the first-stage heat exchanger is shunted into the reboiler of the multi-stage rectifying tower, the temperature of the neon in the rectifying tower is adjusted, separation of 20Ne and 22Ne is promoted, neon branches in the reboiler converge with neon branches cooled by the second-stage heat exchanger, heat in neon at different stages can be fully utilized, and energy consumption is reduced. The neon cooled by the first-stage heat exchanger is used for heat exchange and temperature adjustment of the neon in the rectifying tower, the temperature difference between the neon and the neon is not too large, the temperature of the neon in the rectifying tower can be effectively and finely adjusted, and then separation of isotopes 20Ne and 22Ne at the low temperature is promoted.

This invention discloses a Th / Ra generator containing natural thorium and its production. 224 The Ra method. The generator of this invention includes a cation exchange resin column and bottles I to VI; wherein bottle I is filled with the stock solution; bottle III is filled with deionized water; bottle IV is filled with 4.0–6.0 M nitric acid; bottles II, V, and VI are empty; bottle V is a specially designed collection bottle with an extraction resin column at its opening for collection. 224 Ra. The method of the present invention includes the following steps: 1) using a mixture containing 228 1) A natural thorium mixture of Th and Ra was concentrated to obtain a concentrate, and then the pH of the system was adjusted to serve as the packing stock solution for the Th / Ra generator; 2) The stock solution was passed through a cation exchange resin column to obtain a cation exchange resin column loaded with thorium. 224 Ra, and collect the eluent from the original solution for later use; 3) Elute the cation exchange resin column with inorganic acid. 224 Ra, then the eluent is collected using a special collection bottle to obtain... 224 Ra. This invention enables the separation, purification, and recycling of [product name]. 224 Ra, to overcome 228 Th / 224 The Ra generator has a stringent loading process to avoid the radioactive risks associated with handling tons of natural thorium.

The invention comprises a catalyst device (1) for hydrogen isotope exchange analysis, wherein the catalyst device (1) consists of a catalyst carrier (10) and a catalyst material (20) applied to a surface (12) of the carrier (10), wherein at least the carrier surface (12) consists of an inorganic material and the catalyst material is sputtered or electrodeposited on at least a part of the surface (12) of the carrier (10). The invention further pertains to a sample vessel (100) for hydrogen isotope exchange analysis, wherein the sample vessel (100) contains one or more catalyst devices (1) according to the invention, wherein a maximum outer diameter (D) of the catalyst device (1) is smaller than a minimum inner diameter (101) of an opening of the sample vessel (100) or of the sample vessel (100) itself. The invention also foresees a method of hydrogen isotope analysis employing the sample vessel (100) and the use of the catalyst device (1) in a method of hydrogen isotope analysis.

The invention discloses a hierarchical pore UiO-66 supported crown ether composite material, a preparation method thereof and application of the hierarchical pore UiO-66 supported crown ether composite material in adsorption and extraction of 6Li < + > from complex systems such as salt lake brine. The preparation method comprises the following steps: preparing terephthalic acid, 2-aminoterephthalic acid and a zirconium source through a solvothermal method to obtain a mixed ligand UiO-66, and then pyrolyzing the mixed ligand UiO-66 in an air atmosphere to obtain the hierarchical pore UiO-66; the hierarchical pore UiO-66 and a crown ether solution are mixed and stirred to react for a period of time, then solid-liquid separation is carried out, solids are collected, and the hierarchical pore UiO-66 loaded crown ether composite material is obtained after cleaning and drying. The hierarchical pore UiO-66 loaded crown ether composite material has the advantages of high specific surface area, high dispersion of crown ether adsorption sites, high crown ether loading capacity, high selectivity of 6Li < + > metal ions and the like, and can realize one-step enrichment of 6Li < + > metal ions in complex systems such as salt lake brine.

The invention relates to a cyano polymer material with a rigid framework as well as a preparation method and application of the cyano polymer material. Specifically, the invention provides a cyano polymer with a rigid skeleton as shown in a formula I, and polyethyleneimine (PEI) is grafted on the cyano polymer for modification by using an irradiation crosslinking technology to form a hydrogel adsorption material, so that the hydrogel adsorption material has excellent mechanical strength, moldability and adsorption separation function. The hydrogel material has a good result in the field of molybdenum and technetium separation, provides a new idea for separating < 99m > Tc from < 99Mo, and has a good application prospect.

The present application relates to a tritium water purification device for a reactor, wherein a flash tank is connected to a throttle valve and is used to receive tritium-containing water flowing out of the throttle valve, a heat exchange flow channel is connected to the bottom of the flash tank and is used to heat the bottom of the flash tank so that the flash tank is maintained at a first preset pressure and a first preset temperature, wherein at the first preset pressure, the first preset temperature is higher than or equal to the boiling point of protium-water and lower than the boiling point of tritium-water, so as to achieve primary concentration of the tritium-containing water; a multi-effect distillation tank is used to receive the tritium-containing water that has undergone primary concentration from the flash tank, and the heat exchange flow channel is used to heat the bottom of the multi-effect distillation tank so as to maintain the multi-effect distillation tank at a second preset pressure and a second preset temperature, wherein the second preset pressure is lower than the first preset pressure and the second preset temperature is lower than the first preset temperature, wherein at the second preset pressure, the second preset temperature is higher than or equal to the boiling point of protium-water and lower than the boiling point of tritium-water, so as to achieve secondary concentration of the tritium-containing water.

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 invention relates to the field of medical radioisotope manufacturing technology, and more particularly to a method based on proton beam irradiation. 232 Th target production 212 The method for Pb. The present invention provides a method based on proton beam irradiation. 232 Th target production 212 The method for treating Pb includes the following steps: irradiation with a proton beam. 232 Th target production 228 Th; Dissolved using a mixture of acid and water 232 Th target, allowed to stand, yields the first Th solution; separation from the first Th solution or the pretreated first Th solution... 212 Pb. This invention employs proton beam irradiation. 232 The Th target material method will significantly improve 228 The content of Th was thus significantly increased. 212 The increased production efficiency of Pb fundamentally solves the problems of low output and high cost associated with traditional methods.

To provide a deuterium recycling method and recycling apparatus that can recover and recycle deuterium (D2) contained in exhaust gases emitted from processes utilizing deuterium. [Solution] A method for recycling deuterium, comprising: a recovery step of recovering exhaust gas containing light hydrogen (H2) and deuterium, which is discharged from a process utilizing deuterium (D2), by contacting it with an adsorbent capable of adsorbing them; and a desorption step of desorbing light hydrogen and deuterium from the adsorbent. The desorption step includes a light hydrogen separation step carried out under a first condition in which light hydrogen is preferentially desorbed from the adsorbent, and a deuterium separation step carried out under a second condition in which deuterium is preferentially desorbed from the adsorbent. The method for recycling deuterium according to this disclosure includes a step of supplying the gas containing deuterium obtained in the deuterium separation step as a raw material gas in the process.

A method that includes accelerating ions toward a lattice of carbon fibers and capturing the ions in the lattice of carbon fibers.

A gas separation device for separating and containing various types of gases from a collection chamber based on different atomic masses is disclosed. The chamber is connected to an ion diverter by a valve that, when opened, allows various types of gases to migrate from the collection chamber to an ionizer in which the gases are ionized. The ionized gas is accelerated by the ion accelerator and distributed into the ion deflector. The ion deflector includes a magnetic field within a channel defined by a pair of split-pole magnets. The trajectory of the ions is based on the ion mass of the separated ions. A plurality of collectors are located at different locations on the exit side of the ion deflector for receiving different ions moving along respective trajectories.

To provide a hydrogen isotope separation system capable of achieving stabilization of operation.SOLUTION: A hydrogen isotope separation system 10 comprises an electrolyzer 12, a separator 14, a coupler 15, a circulation flow passage 10e, a pump 18, and a control device 21 which controls the pump 18. The electrolyzer 12 performs electrolysis upon water including heavy water. The separator 14 separates a hydrogen isotope which is discharged from the electrolyzer 12. The coupler 15 generates power with light hydrogen which is discharged from the separator 14. The circulation flow passage 10e connects an anode supply path 10a and an anode discharge path 10c which are provided with respect to an anode 15b of the coupler 15 to which the light hydrogen is supplied while detouring the coupler 15. The pump 18 circulates fluid from the anode discharge path 10c toward the anode supply path 10a in the circulation flow passage 10e.SELECTED DRAWING: Figure 1

The invention provides a conductivity abnormity early warning method and system for radioactive column separation, and relates to the technical field of data processing, and the method comprises the steps: collecting an original conductivity time sequence signal of leacheate in a radioactive column separation process, and carrying out the preprocessing of the original conductivity time sequence signal, and obtaining a denoised reconstructed conductivity signal; the de-noised reconstructed conductivity signals are disassembled into intrinsic mode components, and instantaneous energy and sensitive components of the intrinsic mode components are calculated to obtain a characteristic mode signal set; according to the method, through fusion of modal characteristic analysis of the conductivity signal and spatial correlation verification of multiple ultrasonic parameters, interference introduced by environmental and medium physical property changes is filtered out, and recognition and early warning of early fine abnormal trends in the radioactive column separation process are achieved.

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 application discloses application of a titanium carbide loaded osmium metal hydrogen evolution and deuterium evolution catalyst in water electrolysis separation of hydrogen isotopes, the carrier of the hydrogen evolution and deuterium evolution catalyst is titanium carbide, the active component is osmium metal loaded on the carrier, and the loading amount of the osmium metal is 7-15% of the mass of the carrier. The hydrogen isotope separation efficiency is improved by improving the composition and structure of the hydrogen evolution and deuterium evolution catalyst. The osmium metal is loaded on the titanium carbide base, the hydrogen evolution selectivity is improved and the energy consumption is reduced through strong mutual action of the metal-carrier.

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.