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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 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 7. Отображено 7.
23-05-2023 дата публикации

Method for washing and purifying dirty organic solvent in PUREX process

Номер: CN116153550A
Автор: YANG SULIANG, ZHOU JIN, HAO XUAN, YANG QI, LIU QIAN, ZHU LIYANG, LAN YOUSHI, YANG ZHIHONG, TIAN GUOXIN, LIU RUIYAO
Принадлежит:

The invention discloses a method for washing and purifying a dirty organic solvent in a PUREX process, which comprises the following steps of: carrying out complexing agent-containing acid-base alternate washing on the dirty organic solvent in washing equipment to obtain a purified organic solvent; the method provided by the invention solves the problems that the content of radionuclides in the washed organic solvent in a spent fuel reprocessing plant exceeds the standard, the organic solvent cannot be reused, and the organic solvent cannot be linked with a distillation treatment link; the number of times of cyclic reuse of the organic solvent after chemical washing is increased, and the operation cost is reduced; the content of radionuclide in the distillation feed is reduced, the radioactive level of the distillation residual liquid is reduced, and the pressure of the subsequent distillation residual liquid treatment link is reduced; when the alkaline solution containing the complexing ...

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Номер записи: 1
23-01-2020 дата публикации

METHOD FOR PREPARING GRAPHENE COATING ON THE SURFACE OF METAL

Номер: WO2020015475A1
Автор: HAI, Zhengyin, TIAN, Guoxin, XU, Qian, XIN, Changsheng, YANG, Suliang, WANG, Hui
Принадлежит:

A method for preparing a graphene coating on the surface of a metal, comprising: pretreating the metal surface of a metal sample, immersing, spraying, or hanging and brushing the metal sample, of which the metal surface has been pre-treated, by using an aqueous graphene oxide solution, so that the aqueous graphene oxide solution covers the inner and outer surfaces of the metal sample; baking to dry the metal sample covered with the aqueous graphene oxide solution; performing a microwave reduction treatment on the baked and dried metal sample; and removing the metal sample which has been subjected to the microwave reduction treatment, and washing the metal sample with a cleaning agent, so as to obtain a metal coated with a graphene coating.

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Номер записи: 2
12-09-2017 дата публикации

A soil de - 99 content analysis method

Номер: CN0104536030B
Автор: 杨素亮, 丁有钱, 梁小虎, 宋志君, 孙宏清, 张生栋
Принадлежит:

... 本发明涉及种土壤中锝‑99含量的分析方法，包括如下步骤：干燥、粉碎、过筛等样品预处理操作，称重、灰化、浸取等将锝‑99转移到溶液的操作，锝‑99的分离、富集和纯化，锝‑99的放射性测量。本发明中采用特效固相萃取片法进行锝‑99的分离、富集和纯化，分离、富集和纯化可在半小时内完成，远比传统色层法或沉淀法简便快速；富集有锝‑99的固相萃取片可直接用于放射性测量，避免了采用其他方法分离后必须进行的蒸干再溶解等测量源制备操作，即省去了制备放射性测量源的步骤，使操作更为简便，减少分析人员的工作量。 ...

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Номер записи: 3
09-06-2023 дата публикации

Method for retaining plutonium in dirty solvent in neutral complexing agent elution post-treatment process

Номер: CN116246812A
Автор: YANG QI, YANG SULIANG, LIU QIAN, LIU RUIYAO, ZHOU JIN, HAO XUAN, ZHU LIYANG, TIAN GUOXIN
Принадлежит:

The invention discloses a method for retaining plutonium in a dirty solvent in a neutral complexing agent elution post-treatment process, which comprises the following steps: complexing an acidic solution of a neutral complexing agent TMDGA with Pu (IV) in the dirty solvent, and eluting the plutonium combined with TBP and degradation products HDBP, H2MBP and the like in an organic phase into a water phase; the effective rate of single-stage elution of the TMDGA under different nitric acid concentrations reaches 96.8% or above; the plutonium content in the eluted dirty solvent can reach 1.0 * 10 <-4 > g/L or below, and the requirement of a waste treatment link on the plutonium content in an organic phase is met; the dirty solvent washing method disclosed by the invention can be used for treating the high-plutonium reserved dirty solvent under the abnormal operation condition of a spent fuel reprocessing plant, and can also be used for deeply purifying the dirty solvent under the normal operation ...

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Номер записи: 4
26-05-2023 дата публикации

Method for preparing UO2 fuel microspheres

Номер: CN116168864A
Автор: ZHANG YAN, TIAN GUOXIN, TAN JIWEN, YANG SULIANG, YANG ZHIHONG, LIU QIAN, ZHU LIYANG
Принадлежит:

The invention relates to a method for preparing UO2 fuel microspheres. The method comprises the following steps: preparing a uranium-containing eutectoid, preparing microspheres by adopting a vibration dispersion method or a microfluidic method, denitrifying, reducing and sintering. UO2 fuel microspheres are prepared from uranium-containing eutectoid prepared by taking UNH and urea as raw materials, a gel preparation process of a conventional sol-gel method is replaced, and the density and uranium content of a pelletizing mother solution are improved. According to the method provided by the invention, the pelletizing process flow of the UO2 fuel microspheres can be greatly simplified, and the use of process reagents and the yield of process waste liquid are reduced, so that the preparation method of the UO2 fuel microspheres, which is high in production efficiency and is more economical and safer, is provided.

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Номер записи: 5
02-06-2023 дата публикации

Method for reducing content of plutonium and neptunium in spent fuel post-treatment PUREX process uranium product solution

Номер: CN116200599A
Автор: YANG SULIANG, ZHOU JIN, HAO XUAN, LIU QIAN, YANG QI, YANG YATING, LAN YOUSHI, ZHU LIYANG, YANG ZHIHONG, TIAN GUOXIN
Принадлежит:

The invention discloses a method for reducing the content of plutonium and neptunium in a spent fuel post-treatment PUREX process uranium product solution, which comprises the following steps of: mixing 2DF feed liquid, and washing an extracted organic phase in extraction equipment by using a detergent with complexing and reducing dual effects, so as to reduce the content of the neptunium and the plutonium in the uranium-containing organic phase; a uranium product solution with the content of plutonium and neptunium greatly reduced is obtained through reverse extraction; the method is simple in process, the decontamination coefficient of plutonium and neptunium is 102-104 magnitude after extraction and washing in a 2D tank, and the content of plutonium and neptunium in a uranium product solution is greatly reduced through only one extraction cycle of a uranium line; the requirements on flow operation control precision and solvent quality are reduced, the probability that the uranium product ...

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Номер записи: 6
30-05-2023 дата публикации

Simplified system and method for separating and purifying uranium in irradiation nuclear fuel dissolving solution

Номер: CN116173550A
Автор: YANG SULIANG, HAO XUAN, ZHOU JIN, LIU QIAN, YANG QI, ZHU LIYANG, YANG ZHIHONG, TIAN GUOXIN, LAN YOUSHI, YANG YATING
Принадлежит:

The invention discloses a simplified system and method for separating and purifying uranium in an irradiation nuclear fuel dissolving solution, joint extraction of uranium and plutonium is realized in a 1A extractor, feed liquid 1B + X with dual effects of reduction and complexation is adopted in a 1B + extractor to wash uranium and plutonium co-extraction feed liquid 1AP extracted by the 1A extractor, supplementary extraction is performed by adopting 1B + S, uranium-containing extraction liquid 1B + U obtained by the 1B + extractor, and the uranium-containing extraction liquid 1B + U obtained by the 1B + extractor is used for extracting uranium and plutonium. Carrying out reverse extraction with dilute nitric acid in a 1C extractor to obtain a water-phase uranium solution, the chemical yield of uranium is greater than 99.9%, and carrying out uranium tail end treatment to obtain a uranium product solution; by adopting the method disclosed by the invention, the decontamination of other radionuclides ...

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Номер записи: 7