9 results about "Separation factor" patented technology

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 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.

This invention belongs to the field of boron isotope separation technology, and relates to a fluorinated imidazole ionic liquid, its preparation method, and its application in boron isotope separation. The ionic liquid is based on fluorinated imidazole cations and specific fluorinated anions, with the general chemical formula [R1R2ImR3]. + [RfX] ‑ The structure is designable, non-volatile, and low in toxicity; its properties can be enhanced through targeted molecular design. 10 BF3 / 11 The selective complexation ability of BF3, with a separation coefficient α of 1.035–1.050, is 15%–30% higher than that of traditional processes. Its preparation method is mild and easily scalable, with product purity ≥99.9%. When applied to the separation of BF3 systems, it can stably obtain high abundance. 11 B≥99.9% and 10 Products with a boron content of ≥99% have an ionic liquid regeneration rate of ≥99% and are recyclable with no byproducts. This enables efficient and green separation of boron isotopes, meeting the needs of high-end fields such as the nuclear industry and semiconductors, and has extremely high industrial application value.

The invention discloses a nuclear waste multi-isotope extraction method, an ultra-wide temperature range nuclear battery preparation method and an ultra-wide temperature range nuclear battery preparation system. The nuclear waste multi-isotope extraction method comprises the following steps: 1, crushing operation; 2, sequentially carrying out three-stage gradient extraction on the nuclear waste activated powder by adopting a double crown ether / ionic liquid composite extraction system, a di (2-ethylhexyl) phosphoric acid / tributyl phosphate composite extraction system and a di-isodecyl phosphoric acid / polyethylene glycol 400 composite extraction system; and 3, purification operation. According to the method, mechanical crushing is matched with high-frequency ultrasonic treatment, so that sufficient crushing and surface activation of nuclear waste are realized, and the effect of remarkably improving the subsequent extraction reaction rate and selectivity is achieved. On the basis, the Cs-137, the Am-241 and the Cm-244 are separated step by step by the constructed three-stage gradient extraction module, so that the effects of shortening the separation process and improving the isotope separation factor and selectivity are achieved.

The present disclosure relates to a distillate molecular composition calculation method, device, equipment and storage medium, the method comprising: obtaining molecular composition data of feed of a fractionating device, and distillation range data and yield data of each product distillate, constructing a distillate cutting model based on the distillation range data and yield data, the distillate cutting model comprising temperature intervals, and content data corresponding to each temperature interval, calculating separation coefficients of each distillate in each temperature interval by using a separation coefficient calculation formula based on the distillate cutting model, obtaining a single molecule separation coefficient model, obtaining boiling point data of each single molecule in the feed based on the molecular composition data of the feed, and obtaining the content of each single molecule in each distillate based on the boiling point data and the single molecule separation coefficient model; the single molecule separation coefficient model is obtained through the distillation range data and yield data of the distillate, and the content of the single molecule in each distillate after distillation of the feed can be determined based on the separation coefficient.

This invention relates to a method for isolating thorium from natural sources. 212 Pb / 212 The Bi method belongs to the field of radionuclide separation technology. This invention uses quaternary ammonium salt-type ionic liquids to separate radionuclides... 232 Selective extraction in the Th decay chain 212 Pb / 212 Bi can be rapidly and selectively extracted from Pb via anion exchange in hydrochloric acid medium. 2+ with Bi 3+ , for Th 4+ La 3+ Ba 2+ With almost no extraction, the extraction rate for Pb²⁺ can reach 98.2%, and the Pb / Th separation factor can reach as high as 2700. Even with HCl or HClO₄ back-extraction, the extraction rate remains above 98% after 3-5 back-extractions, and the extractant can be recycled multiple times. This invention's separation method is kineticly fast, highly selective, low-cost, and scalable, obtaining Pb²⁺ from production feedstocks. 212 Pb and 212 Bi has high radiochemical purity, making it suitable for the preparation of targeted alpha therapy radionuclides and effectively solving the clinical supply shortage problem.

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 application discloses a method for rapidly predicting the yield and properties of side cut oil of a constant pressure reduction device, characterized by estimating the initial value of a model separation factor according to the data of the constant pressure reduction device, giving an optimization solution range, calibrating the model separation factor by using actual production data, and predicting the yield of side cut oil of different crude oils after the constant pressure reduction processing based on the calibrated model. Compared with the high requirement of the traditional mechanism model calculation, the method establishes a simplified model and shortens the calculation time. By combining the virtual component division and the application of the distillation separation factor, the simplified calculation and rapid evaluation of the complex distillation process are realized. The method improves the accuracy and efficiency of the evaluation, and provides strong support for the production optimization and cost control of a refining enterprise.

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.