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Application of HDTMA-intercalated bentonites in water waste treatment for U(VI) removal

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Abstract

Bentonite deposits in Slovakia are systematically investigated as potential adsorbents for wastewater and radioactive waste treatment applications. Herein, adsorption properties (isotherms, kinetics and thermodynamics) of raw and organo-modified bentonites towards uranium species in aquaeous solutions were investigated. Organo-modified bentonites was prepared by practical and simple chemical modification method with hexadecyltrimethylammonium bromide (denoted as HDTMA-bentonites). The adsorption processes of U(VI) on HDTMA-bentonites were spontaneous and endothermic, and well simulated by pseudo-second-order model. The maximum adsorption capacity of U(VI) was calculated to be 31.45 mg/g at pH 8.5 and T = 298 K. Slovak bentonites Jelšový potok and Kopernica, their natural and HDTMA-modified forms might be a promising sorbent for the treatment of U(VI) contaminants in aqueous solutions.

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Acknowledgements

This work was supported by the Grant Slovak Research and Development Agency APVV project no. SK-AT-2015-0003 and Agency of the Ministry of Education, Science, Research and Sport of the Slovak Republic and Slovak Academy of Sciences VEGA project no. 1/0507/17. The authors are grateful to the team of Department of Inorganic Chemistry, Aristotle University in Thessaloniki, Greece for professional help and valuable advices.

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Authors and Affiliations

  1. Department of Inorganic Chemistry, Faculty of Natural Sciences, Comenius University in Bratislava, Ilkovičova 6, Mlynská Dolina, 842 15, Bratislava, Slovakia

    Adrián Krajňák, Eva Viglašová, Michal Galamboš & Lukáš Krivosudský

  2. Fakultät für Chemie, Institut für Biophysikalische Chemie, Universität Wien, Althanstr. 14, 1090, Vienna, Austria

    Lukáš Krivosudský

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  1. Adrián Krajňák
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Correspondence to Adrián Krajňák or Michal Galamboš.

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Krajňák, A., Viglašová, E., Galamboš, M. et al. Application of HDTMA-intercalated bentonites in water waste treatment for U(VI) removal. J Radioanal Nucl Chem 314, 2489–2499 (2017). https://doi.org/10.1007/s10967-017-5590-6

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  • DOI: https://doi.org/10.1007/s10967-017-5590-6

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