44 results about "Isotope exchange" patented technology

The invention discloses application of benzo-azacrown ether compounds to separation of lithium isotopes. The benzo-azacrown ether compounds are selected from monoaza15-crown-5, bisaza15-crown-5, triaza15-crown-5 and bisaza18-crown-6. The benzo-azacrown ether compounds serving as extracting agents are dissolved in organic solvents to prepare organic phases, a lithium trifluoroacetate aqueous solution serves as an aqueous phase, and the lithium isotopes are separated at the room temperature by liquid-liquid extraction. The benzo-azacrown ether compounds are easy to dissolve in the organic solvents, efficient separation of the lithium isotopes can be realized by means of liquid-liquid extraction, and considerable separation factors, simplicity and convenience in operation, quickness in isotope exchange and technical simplicity are realized.

The invention relates to the water treatment technical field, in particular to a preparing method and application of an ultra light water, wherein sulfureted hydrogen two-temperature exchange method or other alternative methods are adopted to produce ultra light water; sulfureted hydrogen two-temperature exchange method realizes separation of hydrogen isotopes through adopting multistage concatenation of cooling tower and thermal tower by use of isotope exchange reaction between sulfureted hydrogen and water; liquid raw material water enters from the top of the cooling tower and flows through the cooling tower and the thermal tower from above to below, while gas material sulfureted hydrogen is added from the part between the cooling tower and the thermal tower and circulates inside the cooling tower and the thermal tower from bottom to top inside; heavy components inside the cooling tower is transferred towards liquid phase through chemical exchange so as to be concentrated inside the liquid phase; liquid material with concentrated the heavy components completes chemical exchange with ascending gas during flowing through the thermal tower, thereby, the heavy components are transferred towards gas phase; finally, finished product with lower content of heavy hydrogen can be obtained after liquid phase material discharged from the thermal tower enters into a degassing column to removing sulfureted hydrogen. The invention has the health effects such as delaying aging, radiation resisting, resisting cell mutation, activating immunocyte, improving basal metabolism level of human body, improving sleep, enhancing physical function of male, beauty and body slimming.

The invention discloses a simultaneous upgrading and tritium removal process of heavy water, and belongs to the technical fields of heavy water upgrading and tritium removal. The simultaneous upgrading and tritium removal process of heavy water uses Pt / C / PTFE or Pt-SDB as a catalyst, and employs D2 to conduct isotope exchange with HDO and DTO in heavy water. The process provided by the invention avoids disadvantages of two separate devices in the traditional process for protium and tritium removal in heavy water, achieves simultaneous removal of protium and tritium, effectively reduces production cost and risks in the treatment process; in addition, by identifying key process parameters, the reaction effect of the upgrading and tritium removal process is ensured, effect of each treatment process is improved, and the economic performance of the whole process is improved.

The present invention provides a process whereby pre-enrichment of water streams using a hydrogen source and a catalytic isotope exchange method at one or more remote sites to supply water with augmented deuterium concentration to a central heavy water. This central heavy water plant could be a Combined Electrolysis and Catalytic Exchange (“CECE”) heavy water production plant or a Girdler Sulfide heavy water plant. The deuterium content of water at the remote sites is increased and provides water stream(s) with augmented deuterium concentration to feed to the central heavy water production plant. This could be a first stage of the central CECE deuterium enrichment plant, increasing its capacity for heavy water production approximately in the ratio of its enrichment above natural deuterium concentrations. By relatively simple utilization of available deuterium enrichment capacity at the remote sites, advantages are achieved from a larger scale of heavy water production at the central production plant. The invention further provides systems and methods for adapting chlorate and chlorine dioxide systems which produce hydrogen to additionally produce deuterium-enriched water.

The invention belongs to the technical field of isotope separation, and in particular to a lithium isotope separation method and a single-stage separation factor measurement method thereof. According to the method, lithium isotope separation is realized by utilizing a graphite-organic electrolyte system; the method comprises three steps of oxidation-reduction reaction, isotope exchange reaction and lithium isotope separation. By the method, lithium isotope separation in a non-mercury system is realized; the pollution to an environment and the harm to human health caused by metallic mercury are avoided; the method is easy to operate; moreover, the single-stage separation factor reaches over 1.02, the separation efficiency is high, and the requirement on a single-stage separation factor of lithium isotope separation in industry can be met.

The invention discloses a hydrogen isotope exchange membrane reaction assembly, comprising a palladium composite membrane tube, a corrugated stainless steel tube and an external sleeve, wherein a thermocouple sleeve is in a threaded connection with one end (close to the corrugated stainless steel tube) of the external sleeve and an osmosis gas outlet is mechanically welded at the other end of the external sleeve; a branch pipe serving as a hydrogen isotope exchange raw gas inlet is arranged at the upper end of the thermocouple sleeve; a tail gas outlet is formed at the upper end of the external sleeve and close to the corrugated stainless steel tube, and a carrier gas He and Q2O raw gas inlet is formed at the lower end of the external sleeve far and is away from the corrugated stainless steel tube. According to the hydrogen isotope exchange membrane reaction assembly disclosed by the invention, a small amount of combined deuterium and tritium can be displaced and separated out by using hydrogen isotope exchange reaction, and a part of products are separated in situ out of the system during reaction, so that very high conversion rate and decontamination factors are obtained, and the recovery rate of deuterium and tritium is improved; the hydrogen isotope exchange membrane reaction assembly can be used for treating high-concentration tritium water and treating plasma ash discharge gas in fusion reaction, and can also be used for industrially producing high-purity hydrogen.

The invention belongs to the field of a nuclear air cleaning technology and relates to a novel preparation method of radioactive methyl iodide for detecting active carbon performances and iodine absorber efficiency of a nuclear air cleaning system. The preparation method utilizes an alcohol-water mixed solution of nonradioactive iodomethane as a reagent and comprises the following steps of mixing a prepared nonradioactive iodomethane reactive liquid and a radioactive sodium iodide solution to obtain a radioactive methyl iodide generation liquid, standing the generation liquid for some time so that iodine isotopic exchange is finished and radioactive iodomethane is obtained, putting the radioactive iodomethane generation liquid into a methyl iodide generator, carrying out radioactive iodomethane generation, and injecting the product into a test loop for detecting iodine absorber efficiency. The preparation method prevents a risk caused by use and operation of a large amount of dimethyl sulphate as a highly toxic product, reduces radioactive methyl iodide generator pipe corrosion caused by a test reagent and instability of generator operation caused by corrosion, reduces maintenance frequency of the methyl iodide generator and prolongs a service life of the methyl iodide generator.

The double chemical reflux process for exchanging nitrogen oxide and nitric acid to produce N-15 belongs to the field of high concentration N-15 nitric acid producing technology. Through the chemical reflux in the concentration section and the extraction section, nitrogen oxide and nitric acid produce chemical isotope exchange and circular reflux process is realized. In the extraction section, tail gas nitrogen oxide is recovered with deionized water and oxygen as material in the top refluxer to obtain N-14 nitric acid, and most of the recovered nitric acid is refluxed to the extracting tower for nitrogen isotope exchange to restore the N-15 isotope concentration to natural abundance. The recovered nitric acid is then merged with material nitric cid before being used as the material for the concentration section.

The present invention relates to modification of isotope ratios in peptides and polypeptides as an alternative to full isotopic exchange for coding in proteomics. Subtle modification of isotope ratio does not compromise protein identification experiments and can thus provide elemental composition data for accurate isotope ratio decoding. Application of subtle modification of isotope ratio proteomics (SMIRP) offers a convenient approach to in vivo isotope coding.

The present invention provides a process whereby pre-enrichment of water streams using a hydrogen source and a catalytic isotope exchange method at one or more remote sites to supply water with augmented deuterium concentration to a central heavy water. This central heavy water plant could be a Combined Electrolysis and Catalytic Exchange (“CECE”) heavy water production plant or a Girdler Sulfide heavy water plant. The deuterium content of water at the remote sites is increased and provides water stream(s) with augmented deuterium concentration to feed to the central heavy water production plant. This could be a first stage of the central CECE deuterium enrichment plant, increasing its capacity for heavy water production approximately in the ratio of its enrichment above natural deuterium concentrations. By relatively simple utilization of available deuterium enrichment capacity at the remote sites, advantages are achieved from a larger scale of heavy water production at the central production plant. The invention further provides systems and methods for adapting chlorate and chlorine dioxide systems which produce hydrogen to additionally produce deuterium-enriched water.

The invention relates to a method for preparing O-nitric acid, comprising the following steps of: (1) carrying out oxygen isotope exchange reaction between nitric acid material and oxygen-18 water in a sealed reaction kettle at the temperature between 50 DEG C and 80 DEG C for 1 to 10 days; (2) introducing ammonia gas to solution obtained after reaction for neutralization and removing oxygen-18 water with reduced abundance ratio through distillation at reduced pressure to obtain O-ammonium nitrate crystals in the reaction kettle; and (3) adding excessive acid to the reaction kettle to fully dissolve the O-ammonium nitrate crystals in the reaction kettle so as to regenerate O-nitric acid, and carrying out distillation at reduced pressure again to distill the regenerated O-nitric acid into liquid nitrogen trap so as to obtain the O-nitric acid product. Compared with the prior art, the invention has the advantages of simple process, easy operation, low energy consumption, high purity of products and low loss of O and the like.

The invention relates to a fluorinated phosphine oxide compound used in the preparation of a positron emission imaging agent and a preparation method thereof, and has a structure shown in a formula I.For the first time, fluorinated phosphine oxide is used as an 18F-labeled auxiliary group, a positron nuclides probe is constructed by a 18F-19F isotope exchange strategy, a labeling method is mild in conditions, reactions can be directly conducted in an 18F-aqueous solution without blow-drying 18F-, and the compound has high radiochemical yield, easy purification, no need for high performance liquid chromatography separation and purification and broad application prospects in the field of positron drugs of preparing biomolecules such as heat sensitive and solvent sensitive peptides or proteins and the like.

An isotope enrichment method comprising the step of performing the isotope exchange between an aqueous solution containing at least two components each represented by the formula: H₂O—H₂SiF6·nSiF₄ (wherein n≧0) and a gas containing SiF₄ to enrich a stable Si isotope.

The invention discloses a method and a system for simultaneously producing high-concentration boron-10 boron trifluoride and high-concentration boron-11 boron trifluoride. With a small amount of commercially available bottled boron trifluoride as a material and a boron trifluoride/nitromethane or ether compound as a boron isotopes exchange working system, by cold-heat reflux at a concentration station and an extraction station in a cascade device, the boron trifluoride and a complex produced by the nitromethane or ether compound absorbing the boron trifluoride undego boron isotopes exchange, realizing the circulating reflux separation of boron-10 and boron-11. The system has a compact structure, is easy to operate, can be easily continuously automated, and not only greatly reduces the dosage of the boron trifluoride material, but also solves the problem of waste boron trifluoride discharge, moreover, energy consumption is reduced by about 80 percent, energy saving and zero discharge are realized, the production cost is greatly reduced, and the concentrations of the obtained boron-10 and boron-11 products are higher than or equal to 99 atom percent.

The invention relates to a stable isotope low-temperature separation and concentration device and technology. The technology comprises the following steps that purified high-purity feed gas enters a low-temperature separation and concentration device formed by the series connection of n difunctional composite separation towers from a buffer tank through pump metering, and each tower top provides an initial liquid phase of the tower corresponding to a condenser; and each tower bottom provides an initial vapor phase of the tower corresponding to a reboiler, vapor and liquid are in countercurrentcontact in each tower, two processes of isotope exchange reforming and vapor-liquid rectification are continuously and alternately carried out, a heavy isotope product is continuously produced at thelast nth-stage tower bottom through pump metering, and waste gas subjected to heavy isotope separation is continuously produced at the first-stage tower top condenser through pump metering. The device is a cascade system formed by connecting n bifunctional composite separation towers which are horizontally arranged in series, and each bifunctional composite separation tower is composed of m towersections; and the device and the technology effectively overcome the defects of single function and the like of the separation tower in the traditional low-temperature rectification process, reduce the number of cascaded towers, simplify the process and save the energy consumption.