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Небесная энциклопедия

Космические корабли и станции, автоматические КА и методы их проектирования, бортовые комплексы управления, системы и средства жизнеобеспечения, особенности технологии производства ракетно-космических систем

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Мониторинг СМИ

Мониторинг СМИ и социальных сетей. Сканирование интернета, новостных сайтов, специализированных контентных площадок на базе мессенджеров. Гибкие настройки фильтров и первоначальных источников.

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Применить Всего найдено 9. Отображено 9.
09-06-2023 дата публикации

Amide extracting agent as well as preparation method and application thereof

Номер: CN116239490A
Автор: CHEN QI, LI BAOLE, HE TIANSHENG, GE XIAO, WANG JUNLI, WANG WENTAO, YAN TAIHONG, LV HONGBIN, CAO ZHI
Принадлежит:

The invention discloses an amide extracting agent as well as a preparation method and application thereof. The bisamide extraction agents 2, 2 '-(cyclohexane-1, 2-dialkyl bis (oxy)) bis (N, N-bis (2-ethylhexyl) acetamide) (Octy-CDA) and 2, 2'-(cyclohexane-1, 2-dialkyl bis (oxy)) bis (N, N-dioctyl acetamide) (2-ethylhexyl-CDA) are obtained by adopting a two-step method, the preparation raw materials of the amide extraction agents are easy to obtain, the reaction is carried out at normal temperature and normal pressure, and the reaction process is clean and environment-friendly; the bisamide extraction agent has ether oxygen bonds and carbonyl oxygen bonds in the structure, more binding sites are provided for plutonium extraction, and the coordination ability is improved; moreover, the amide extraction agent disclosed by the invention is convenient to dispose wastes after plutonium extraction, so that environmental pollution is reduced.

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Номер записи: 1
12-05-2023 дата публикации

Flocculation device suitable for radioactive feed liquid

Номер: CN116110632A
Автор: LI TIANCHI, HE HUI, YAN TAIHONG, LIU FANG, SUN YANDONG, ZHOU JIA, BAI YANG, ZHANG QIUYUE, GUO JIANHUA, CHANG SHANGWEN, LI GAOLIANG, SU XING, TANG HONGBIN
Принадлежит:

The invention belongs to the technical field of spent fuel post-treatment, and particularly relates to a flocculation device suitable for radioactive feed liquid, which comprises a flocculation basin (27) connected with a flocculant feeding section and a radioactive feed liquid feeding section, the flocculation basin (27) is used for stirring a flocculating agent provided by the flocculating agent feeding section and radioactive feed liquid provided by the radioactive feed liquid feeding section to obtain mixed liquid. According to the flocculation device, the pressure conditions of each pipeline and each part in the starting and stopping states are considered, the tank body is flushed by designing the movable partition plate, and the flocculation device is safe, convenient to clean and maintain and suitable for the radioactive feed liquid.

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Номер записи: 2
04-04-2023 дата публикации

Method for separating trace plutonium from large amount of uranium by using solid-phase extraction resin

Номер: CN115896491A
Автор: WANG JUNLI, WANG HUI, YAN TAIHONG, WANG WENTAO, HE TIANSHENG, ZHENG WEIFANG
Принадлежит:

The invention relates to a method for separating trace plutonium from a large amount of uranium by using solid-phase extraction resin, and belongs to the field of spent fuel post-treatment. The method comprises the following steps: preparing spent fuel post-treatment simulation feed liquid containing uranium and plutonium, pumping the spent fuel post-treatment simulation feed liquid into an extraction resin column at a first preset flow rate, and carrying out a dynamic test; analyzing the concentration of uranium and plutonium in the water phase at the outlet at set intervals, and drawing a penetration curve; and pumping an eluting agent into the extraction resin column after adsorption equilibrium at a second preset flow rate, and carrying out plutonium elution by using the eluting agent. According to the method disclosed by the invention, the trace plutonium in a large amount of uranium is efficiently separated and purified by adopting an extraction chromatography method which has the ...

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Номер записи: 3
07-09-2018 дата публикации

METHOD FOR RECYCLING PLUTONIUM FROM SPENT RADIOACTIVE FUEL

Номер: WO2018157424A1
Автор: ZUO, Chen, ZHENG, Weifang, YAN, Taihong
Принадлежит:

Provided is a method for recycling plutonium from a spent radioactive fuel. The method successively comprises the following steps: extraction: tetravalent plutonium is extracted from an aqueous solution of the spent radioactive fuel using an organic solvent containing tributyl phosphate; reduction of plutonium with a reducing reagent: an organic solvent containing dimethyl hydroxylamine is added into an organic phase, so as to reduce the tetravalent plutonium into trivalent plutonium; and back extraction: an aqueous dilute acid solution is added into the organic phase so as to re-extract plutonium into the aqueous phase for recycling. The use of the method for recycling plutonium from a spent radioactive fuel can significantly improve the efficiency of recycling plutonium from a spent radioactive fuel with respect to HAN back extraction, and at the same time, can avoid the problems resulting from U (IV) reduction and extraction.

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Номер записи: 4
30-06-2023 дата публикации

Method for extracting technetium from nuclear fuel post-treatment waste liquid by adopting extraction method

Номер: CN116356145A
Автор: WANG HUI, WANG JUNLI, SHEN ZHEN, YAN TAIHONG, HE TIANSHENG, GE XIAO
Принадлежит:

The invention relates to a method for extracting technetium from nuclear fuel post-treatment waste liquid by adopting an extraction method. Comprising the following steps: preparing a technetium-zirconium co-extraction feed, co-extracting technetium and zirconium by taking a TBP-kerosene organic solution as an extracting agent, reducing and back-extracting technetium in a TBP organic phase co-extraction solution by adopting a reduction back-extraction agent, and back-extracting zirconium in the residual TBP organic phase by using a complexing back-extraction agent; the current situation that in the prior art, when technetium is extracted from nuclear fuel post-treatment waste liquid through an extraction method, more organic-phase radioactive waste liquid except tributyl phosphate can be generated, and a set of solvent treatment system needs to be additionally arranged is improved, introduction of extra solvents and metal ion groups into the post-treatment system can be avoided, and the ...

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Номер записи: 5
23-06-2023 дата публикации

Preparation method and application of supramolecular adsorption material

Номер: CN116272905A
Автор: WANG WENTAO, HU YIFU, YAN TAIHONG, ZHANG YE, SU ZHE, YUAN JIEQIONG
Принадлежит:

The invention discloses a preparation method and application of a supramolecular adsorption material, cyclodextrin and an amphiphilic organic ligand are self-assembled to form the supramolecular adsorption material, and according to the subject-object recognition effect of cyclodextrin, a hydrophobic cavity of the supramolecular adsorption material coats a hydrophobic molecule or a hydrophobic part of the molecule, so that the supramolecular adsorption material is formed. The ligand has a hydrophobic functional group with a proper size and can enter a hydrophobic cavity of cyclodextrin so as to form a compound; and cooling at a specific temperature, and crystallizing at a constant temperature to obtain the cyclodextrin supramolecular adsorption material. The preparation process does not involve complex organic reaction, the cost is low, and the prepared supramolecular adsorption material is good in performance, high in expansibility and easy for large-scale production; the supramolecular ...

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Номер записи: 6
16-05-2023 дата публикации

Device and method for oxidative volatilization of spent fuel in hot chamber

Номер: CN116130138A
Автор: SUN YANDONG, LIU FANG, BAI YANG, GUO JIANHUA, YANG DONGXUE, YUAN ZHONGWEI, LI TIANCHI, ZHOU JIA, ZHANG QIUYUE, YAN TAIHONG, ZHENG WEIFANG
Принадлежит:

The invention belongs to the technical field of spent fuel post-treatment, and particularly relates to a device and a method for oxidative volatilization of spent fuel in a hot chamber, the device is used for oxidative volatilization treatment of the spent fuel, and the device comprises a sealed heating furnace body (2) arranged in the hot chamber and a reaction tank (3) arranged in the heating furnace body (2), the heating furnace body (2) can be remotely controlled outside the hot chamber; the device is simple in structure, small in occupied area and convenient to operate in a hot chamber through a mechanical arm, spent fuel oxidation and cladding and powder separation can be effectively achieved through the device and the method, follow-up cladding and powder analysis is greatly facilitated, and the device and the method have great significance in promoting oxidative volatilization related research.

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Номер записи: 7
28-07-2023 дата публикации

Decontamination composite solution and preparation method and application of gel film of decontamination composite solution

Номер: CN116504432A
Автор: WANG WENTAO, WANG JUNLI, YAN TAIHONG, HU YIFU, ZHANG YE
Принадлежит:

The invention discloses a decontamination composite solution and a preparation method and application of a gel film of the decontamination composite solution, a hydrophobic cavity of the decontamination composite solution is realized by'wrapping 'hydrophobic molecules or hydrophobic parts of molecules according to the subject-object inclusion effect of cyclodextrin, and the volume of the hydrophobic parts/functional groups of complexing agent molecules is smaller than that of a cyclodextrin cavity. The complexing agent and cyclodextrin form a compound so as to be well dispersed into a solution, and the complexing agent with good coordination ability to radioactive ions and cyclodextrin can almost generate an inclusion compound. Polysaccharide molecular chains are rich in hydrophilic functional groups such as hydroxyl groups and amino groups, so that the gel film has good hydrophilicity, small ion transmission resistance and short balance time, and the functional groups such as hydroxyl ...

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Номер записи: 8
25-07-2023 дата публикации

Preparation method of noble metal catalyst, catalyst and application

Номер: CN116474767A
Автор: LI BAOLE, CAO ZHI, ZUO CHEN, HE TIANSHENG, GE XIAO, YAN TAIHONG, ZHENG WEIFANG
Принадлежит:

The invention relates to a preparation method of a noble metal catalyst, the catalyst and application, and belongs to the technical field of nuclear power waste governance, the method comprises the following steps: S1, dispersing activated carbon in a nitric acid solution for impregnation and adsorption to obtain first activated carbon, and then drying to obtain a first activated carbon carrier; s2, dispersing the first activated carbon carrier in a hydrochloric acid solution for impregnation and adsorption to obtain second activated carbon, and then drying to obtain a formed activated carbon carrier; s3, mixing the formed activated carbon carrier with a corresponding active component solution, dipping and adsorbing at room temperature, and performing rotary evaporation to remove a solvent to obtain a dry material; s4, roasting the dried material in a reducing environment, cooling and then collecting; and S5, fully washing and filtering the collected material in deionized water, and finally ...

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Номер записи: 9