Liquid–liquid extraction of neptunium(VI) and neptunium(V) from carbonate solutions by methyltrioctylammonium carbonate in toluene

Boyarintsev, A. V.; Перевалов, С. А.; Stepanov, S. I.; Чекмарев, А. М.

doi:10.1007/s10967-020-07487-w

Cited by 6 publications

(4 citation statements)

References 21 publications

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“…The highest concentration of uranium in the aqueous phase in this work was 45 gU/L. There are also a few extractions reported in the literature ,− ,, using solutions exceeding 60 gU/L. However, in the CARBEX process, additional measures such as ultrasound , can be employed to enhance uranium dissolution and increase its concentration in the solution to nearly 300 gU/L.…”

Section: Resultsmentioning

confidence: 99%

“…In carbonate systems with MTOAC solutions in nonpolar solvents, the hydration of the extractant plays the largest role in the nonideality of the organic phase, reflected by the activity coefficient. Therefore, the equation fitted by the GSA method should be changed to eq ln nobreak0em.25em⁡ D = n .25em ln [ c R 0 + false( h normali + h ∞ false) · a W ] + const where h i and h ∞ are the degree of hydration of MTOAC in toluene at a given concentration and at infinite dilution, with water activity of a W = 1. Based on the literature, we can obtain h i and h ∞ .…”

Section: Resultsmentioning

confidence: 99%

Section: The Effect Of Concentration Of Mtoac and Determination Of Th...mentioning

confidence: 99%

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Recovery of Uranium in a Carbonate Solution Using Methyltrioctylammonium Carbonate as the Extractant

Fang,

He,

Jiao

et al. 2024

Ind. Eng. Chem. Res.

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The CARBEX process, proposed in 2008, is a spent nuclear fuel reprocessing method that relies on the alkaline environment of a carbonate-hydrogen peroxide system. The extraction stage is the most important step and is mainly used for the separation of nuclides. In this work, we focused on the extraction stage of the CARBEX process, using methyltrioctylammonium carbonate as an extractant to extract uranium from the carbonate solution. The effects of the concentration of uranium (0.02−0.17 mol/L) and carbonate (0.5−1.2 mol/L) in an aqueous solution, extractant concentration (0.1−0.6 mol/L), phase volume ratio (3:1−1:3), and temperature (25−60 °C) on the extraction distribution ratio were studied. The results show that the concentration of carbonate has a great influence on extraction, and the distribution ratio increases rapidly with the decrease of the concentration of carbonate in the aqueous phase. In addition, we investigated the potential of the extractant. The extractant can reach a distribution ratio of 0.78 in the presence of a high concentration (292.9 gU/L) of uranium in the aqueous solution. In the end, we deduced the extraction mechanism, and the extraction reaction equation was given.

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Section: Resultsmentioning

confidence: 99%

Section: Resultsmentioning

confidence: 99%

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Recovery of Uranium in a Carbonate Solution Using Methyltrioctylammonium Carbonate as the Extractant

Fang,

He,

Jiao

et al. 2024

Ind. Eng. Chem. Res.

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“…Although there are many examples on rare earth separation, [24][25][26][27][28][29][30] there are only a few examples of separation processes in general using carbonate medium. These examples consist of extraction of lanthanides and transplutonium elements from alkaline and carbonate media can be achieved mainly via liquid-liquid extraction, [31][32][33][34][35][36] using various extractants such as quaternary ammonium salts, [37][38][39] primary amines 40 or alkylpyrocatechols. 41 There are also just a few examples of using extraction chromatography in carbonate media.…”

Section: Introductionmentioning

confidence: 99%

Separation of terbium as a first step towards high purity terbium-161 for medical applications

Arman,

Mullaliu,

Geboes

et al. 2024

RSC Adv.

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Polyamidoxime‐Coated Coconut Haustorium Derived Magnetic Biochar Adsorbent with Photothermal Conversion for Highly Efficient Uranium Recovery from Nuclear Wastewater

Zhou,

Gao,

Liu

et al. 2024

Adv Funct Materials

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Efficient removal of uranium from uranium‐containing nuclear wastewater is of great significance for utilizing uranium resources and protecting the environment from uranium hazards. In this paper, a polyamidoxime‐coated coconut haustorium derived magnetic biochar (CHMBC‐PAO) composite adsorbent with excellent adsorption performance, magnetism, recyclability, and photothermal conversion properties in complex environments is prepared through a simple soak‐gelation coating method for efficient removal of uranium from nuclear wastewater. The coconut haustorium biochar, carbonized by a sponge‐like organ inside the sprouted coconut, can provide rich functional groups and electronegative surface, which are conducive to the loading of functional materials and the adsorption of uranyl, respectively. The CHMBC‐PAO presents 2.4 emu g−1 saturation magnetization, making it can be efficiently recovered through magnetic recovery. It can convert absorbed light into thermal energy through molecular thermal vibration and non‐radiative relaxation process of excitons. Enhanced by the photothermal effect, CHMBC‐PAO shows an extra high uranium adsorption capacity of 310.30 mg g−1 in acidic nuclear wastewater within a short period of time, surpassing the adsorption capacity of most reported uranium removal materials. Meanwhile, the CHMBC‐PAO also presented excellent ion selectivity and reusability. Therefore, CHMBC‐PAO composite adsorbent can be considered as a potential candidate for treating radioactive nuclear wastewater.

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Liquid–liquid extraction of neptunium(VI) and neptunium(V) from carbonate solutions by methyltrioctylammonium carbonate in toluene

Cited by 6 publications

References 21 publications

Recovery of Uranium in a Carbonate Solution Using Methyltrioctylammonium Carbonate as the Extractant

Recovery of Uranium in a Carbonate Solution Using Methyltrioctylammonium Carbonate as the Extractant

Separation of terbium as a first step towards high purity terbium-161 for medical applications

Polyamidoxime‐Coated Coconut Haustorium Derived Magnetic Biochar Adsorbent with Photothermal Conversion for Highly Efficient Uranium Recovery from Nuclear Wastewater

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