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Wyszukujesz frazę "CYANEX 272" wg kryterium: Temat


Wyświetlanie 1-2 z 2
Tytuł:
Application of Hollow Fiber Supported Liquid Membrane for Extraction of Cobalt by Cyanex 272
Autorzy:
Swain, Basudev
Lee, Jae-Chun
Kim, Dae-Guen
Lee, Chan Gi
Powiązania:
https://bibliotekanauki.pl/articles/354650.pdf
Data publikacji:
2019
Wydawca:
Polska Akademia Nauk. Czytelnia Czasopism PAN
Tematy:
Cyanex 272
hollow fiber supported
cobalt recovery
Opis:
Considering the advantages of hollow fiber supported liquid membrane (HFSLM), it has been applied for extraction of Co(II) with a motivation to extract cobalt from various waste resources. Extraction efficiency and transport behavior of Co(II) through HFSLM containing Cyanex 272 diluted in kerosene were investigated. Experiments were performed as a function of aqueous feed solution velocity (1000 mL/min) for both feed and strip, pH of feed solution in the range of 4.00-6.75, the carrier concentration of 25-1000 mol/m3, and acid concentration in strip solution of 1-500 mol/m3 on. The mass transfer rate or flux J Co(II), which is a function of metal concentration, volume of solution, and membrane area were analyzed. The optimum condition for extraction of Co(II) was pH of 6.00, Cyanex 272 concentration of 500 mol/m3 and H2 SO4 concentration of 100 mol/m3.
Źródło:
Archives of Metallurgy and Materials; 2019, 64, 3; 845-850
1733-3490
Pojawia się w:
Archives of Metallurgy and Materials
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Applicability Study of Co and Eu Extraction Using Solvent from Ca Rich HCl Solution
Autorzy:
Oh, Maengkyo
Lee, Keunyoung
Foster, Richard I.
Kim, Ik-Soo
Lee, Chang-Ha
Powiązania:
https://bibliotekanauki.pl/articles/2203724.pdf
Data publikacji:
2023
Wydawca:
Polska Akademia Nauk. Czytelnia Czasopism PAN
Tematy:
solvent extraction
radioactive wastewater
waste valorization
Cyanex 272
Cyanex 301
Opis:
This study was conducted to treat radioactive acidic wastewater, which contained radioactive 60Co and 152Eu. The wastewater can be generated during a decommissioning project to reduce the volume of radioactive concrete waste from nuclear facilities. With a variety of methods for separating the radioactive nuclides available, we evaluated the separation applicability of the solvent extraction method. From our results, Co and Eu could be easily extracted from the Ca rich wastewater using Cyanex301 (Co extraction (%) 99.8, Eu extraction (%) 99.6) without Ca extraction. On the other hand, Eu could be selectively separated by Cyanex272 (Eu extraction (%) 99.1) without Co and Ca extraction at pH 2~3. Therefore, the extraction method can be tailored according to the target radionuclides present in the wastewater and be selectively applied to the overall treatment process. By extracting radioactive Co and Eu from acidic wastewater to below the discharge criteria, treated wastewater could be regarded as non-radioactive industrial waste, to be economically and easily handled. Moreover, it may be possible to reuse separated Co and Eu for research and industrial applications by realizing waste valorization.
Źródło:
Archives of Metallurgy and Materials; 2023, 68, 1; 123--126
1733-3490
Pojawia się w:
Archives of Metallurgy and Materials
Dostawca treści:
Biblioteka Nauki
Artykuł
    Wyświetlanie 1-2 z 2

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