Liquid–liquid extraction of trivalent americium from carbonate and carbonate–peroxide aqueous solutions by methyltrioctylammonium carbonate in toluene

Author:

Boyarintsev Alexander V.ORCID,Kostikova Galina V.,Stepanov Sergei I.,Chekmarev Alexander M.,Tsivadze Aslan Yu.

Funder

Dmitry Mendeleev University of Chemical Tecnology of Russia

Publisher

Springer Science and Business Media LLC

Subject

Health, Toxicology and Mutagenesis,Public Health, Environmental and Occupational Health,Spectroscopy,Pollution,Radiology Nuclear Medicine and imaging,Nuclear Energy and Engineering,Analytical Chemistry

Reference36 articles.

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3. Kim KW, Kim YH, Kim SM, Seo HS, Chung DY, Yang HB, Lim JK, Joe KS, Lee EH (2008) A study on a process for recovery of uranium alone from spent nuclear fuel in a high alkaline carbonate media. NRC 7, Budapest, Hungary

4. Stepanov SI, Chekmarev AM (2008) Concept of spent nuclear fuel reprocessing. Dokl Chem 423(1):276–278

5. Soderquist CZ, Johsen AM, McNamara BK, Hanson BD, Chenault JW, Carson KJ, Peper SM (2011) Dissolution of irradiated commercial UO2 fuels in ammonium carbonate and hydrogen peroxide. J Ind Eng Chem Res 50:1813–1818

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