10 results about "Isotope exchange" patented technology

This invention discloses a method for detecting hydrogen deuteride after water-hydrogen isotope liquid-phase catalytic exchange. The apparatus used in this method includes a first Erlenmeyer flask, a metering pump, a catalytic exchange bed, a flow meter, and a time-of-flight mass spectrometer. The detection process is as follows: a mixture of heavy water and purified water is filled into the first Erlenmeyer flask; a hydrophobic catalyst and hydrophilic filler for the isotope exchange reaction are filled into the catalytic exchange bed; the mixed water enters the catalytic exchange bed from the top and undergoes an isotope exchange reaction with hydrogen gas entering from the bottom of the bed; the deuteride gas after the exchange reaction is directly introduced into the time-of-flight mass spectrometer for detection via the flow meter. This method can monitor the changing trend of deuteride gas after water-hydrogen isotope liquid-phase catalytic exchange online. Simultaneously, the performance of the catalyst, the packing ratio, and the packing method can be examined, thereby further guiding the process. This method features fast analysis speed and high sensitivity.

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.

This invention discloses an N-substituted pyridine fluoroborate inner salt reagent, its preparation method, and its application in the preparation of F-18 radiopharmaceuticals. The N-substituted pyridine fluoroborate inner salt reagent is obtained by reacting protonated pyridine fluoroborate of Formula I with a compound of Formula II in the presence of a solvent. This inner salt reagent, through a substituted alkyl group linked to the pyridine N-phase, can undergo a coupling reaction with molecules containing specific groups (including drug molecules or their derivatives) to generate F-18 radiopharmaceutical precursors. Further isotope exchange reactions yield the F-18 radiopharmaceutical. By adjusting the types of substituents in the substituted alkyl group, this invention can achieve the construction of structurally diverse F-18 radiopharmaceutical precursors with different drug molecules or their derivatives. Furthermore, the prepared F-18 radiopharmaceutical precursors exhibit good stability in aqueous phase and can undergo efficient reactions in aqueous buffer solutions. 18 F- 19 The F isotope exchange reaction avoids the time-consuming dehydration process in the traditional F-18 radiopharmaceutical synthesis, greatly shortening the synthesis time and thus effectively improving the efficiency of F-18 radiopharmaceutical synthesis. 18 F-labeling rate.

This application provides a method for preparing electronic-grade deuterated ammonia, belonging to the field of electronic specialty gas manufacturing technology. The preparation method of electronic-grade deuterated ammonia includes the following steps: S1 Ammonia gas and heavy water raw materials are fed into an exchange distillation column for isotope exchange reaction; S2 After the exchange distillation column reaches equilibrium, the first crude deuterated ammonia is fed into a de-heavy distillation column for de-heavy treatment; S3 After the de-heavy distillation column reaches equilibrium, the second crude deuterated ammonia is fed into an enrichment distillation column for isotope enrichment, so that hydrogen isotope-enriched ammonia is enriched at the top of the enrichment distillation column, and deuterated ammonia is enriched at the bottom of the enrichment distillation column; S4 After the enrichment distillation column reaches equilibrium, hydrogen isotope-enriched ammonia is discharged from the top of the enrichment distillation column, and deuterated ammonia is discharged from the bottom of the enrichment distillation column and collected to obtain electronic-grade deuterated ammonia. This preparation method has the advantages of low cost, high deuterium atom utilization rate, and mild and controllable reaction conditions.

The invention discloses a method for measuring an element distribution coefficient and an isotope fractionation value between a fluid and a melt, and belongs to the field of stable isotope geochemistry, and the method comprises the following steps: preparing an initial fluid and an initial solid phase; performing isotope exchange reaction by using the initial fluid and the initial solid phase; an experimental fluid phase and an experimental melt phase in a reaction product are separated through freezing and deionized water cleaning; and determining the metal element content and stable isotope composition of the experimental fluid phase and the experimental melt phase, and calculating the metal element distribution coefficient and isotope fractionation value between the experimental fluid phase and the experimental melt phase. According to the method, after isotope exchange equilibrium of the rapid quenching cold-sealed autoclave, the fluid phase and the silicate rock phase are frozen and then separated, the fluid phase and the silicate rock phase are precisely separated and recovered through multi-step deionized water cleaning, precise analysis of the metal element content and the isotope composition of the two phases is achieved, and the analysis precision of the metal element content and the isotope composition of the two phases is improved. And the method has positive significance on isotope geochemistry development.

This invention provides a hydrogen isotope exchange catalyst composite and a method for producing the same, which are highly practical in terms of their applicability. This composite possesses hydrophobic properties, preventing the phenomenon of liquid water covering the catalyst while simultaneously not hindering water molecules from approaching the catalyst, and ensuring very good efficiency in the hydrogen isotope exchange reaction. Furthermore, it ensures excellent reaction efficiency without depending on the hydrophobicity of the matrix. [Solution] A catalyst complex for hydrogen isotope exchange is provided, comprising a catalyst support containing a metal-organic structure composite having an open metal site (OMS) and pores; a hydrophobic modifying compound introduced into the OMS; and a metal catalyst for hydrogen isotope exchange introduced into the pores.

The invention relates to a method for measuring the molecular content of H2O, HDO and D2O in heavy water by using an attenuated total reflection infrared absorption spectrum, which comprises the following steps: assembling a device comprising a Fourier transform infrared spectrometer and an ATR (Attenuated Transform Resonance) component, enabling interference light to pass through a reflecting lens to a crystal, and reflecting to a detector after total reflection; preparing a series of initial concentration heavy water solution standard samples; standing or heating the standard sample to isotope exchange equilibrium, and calculating theoretical concentration; testing the standard sample to obtain the characteristic peak areas of 1640 cm <-1 > (H2O), 1200 cm <-1 > (D2O) and 2500 cm <-1 > (O-D), and making a standard curve; and testing a blind sample and substituting into the curve to obtain the content. According to the method, the problems that the O-H peak of the high-concentration water sample is saturated and the molecular morphology of HDO and D2O cannot be distinguished in the traditional infrared spectroscopy are solved, accurate quantification is realized, and a reliable molecular level detection means is provided for the fields of nuclear industry and the like.

Provided is a deuterated ammonia production device with which deuterated ammonia can be economically and efficiently produced by means of a flow system without requiring a catalyst or a post-stage separation process caused by the supply of a large amount of a carrier gas.　One aspect of the present invention is a deuterated ammonia production device comprising an absorption tower section composed of one or more stages of absorption towers, wherein: the absorption tower section has a filling material part composed of a filling material, an ammonia gas introduction part for introducing ammonia gas, a deuterated solvent introduction part for introducing a deuterated solvent, a deuterated ammonia gas discharge part for discharging deuterated ammonia gas, and a deuterated solvent discharge part for discharging a depleted deuterated solvent; and in the absorption tower section, the ammonia gas flows upward in the filling material part while the deuterated solvent flows downward in the filling material part, whereby absorption of the ammonia gas into the deuterated solvent and an isotope exchange reaction are performed in the filling material part to generate the deuterated ammonia gas.

This invention relates to a method, system, and application for the gas-carrier synergistic treatment of tritium wastewater. The method is a three-stage synergistic extraction and removal of tritium involving gas, liquid, and solid phases, comprising at least one single-stage treatment process. In this single-stage process, an appropriate amount of carrier gas is introduced into a solid-liquid adsorption system, and a gas-liquid-solid three-phase contact structure is constructed. The adsorption and isotope exchange of tritium-bearing water by the solid adsorbent material enriches tritium in the solid adsorbent material. Simultaneously, the carrier gas, through gas-liquid interface renewal and gas-liquid mass transfer, carries away water from the liquid phase as water vapor, forming a carrier gas flow carrying tritium-bearing water vapor, ultimately achieving tritium wastewater separation. The system of this invention has a simple structure and mild operating conditions; it significantly improves the single-stage tritium removal rate and adsorption capacity per unit mass under normal pressure and low temperature conditions, while also possessing the characteristics of simple structure, low energy consumption, and ease of engineering scale-up.

This invention belongs to the field of isotope separation technology, specifically disclosing a method for lithium isotope separation. Addressing the significant risks to the ecological environment and occupational health posed by existing lithium amalgam methods due to the use of large quantities of highly toxic metallic mercury, and the limitation of insufficient mercury availability hindering large-scale production to meet the increasing demand for lithium isotope products, this invention proposes a safe, efficient, and industrially viable non-mercury-based lithium isotope separation method. This method is a liquid-liquid extraction method based on isotope exchange reactions between molten salt and liquid metal. The basic principle utilizes two stable isotopes of lithium. 6 Li and 7 The difference in the partition coefficient of Li between the liquid metal phase and the molten salt phase. The single-stage separation coefficient α of this method can meet the requirements of the single-stage separation factor for the industrialization of chemical exchange method (α≥1.02), and can be realized by laboratory heating furnace or scaled up by high-temperature extraction tower, providing a new technical route for lithium isotope separation.