4.7 Article

Preparation and characterization of oxidized graphene for actinides and rare earth elements removal in nitric acid solutions from nuclear wastes

Journal

JOURNAL OF MOLECULAR LIQUIDS
Volume 335, Issue -, Pages -

Publisher

ELSEVIER
DOI: 10.1016/j.molliq.2021.116260

Keywords

Actinides and rare earth elements; Nuclear wastes; Sorption; Oxidized multilayer graphene; Distribution coefficient

Funding

  1. King Saud University [RG-1438-014]
  2. Ministry of Education and Science of the Russian Federation [0090-2019-0008]
  3. Project of the State Assignment (Vernadsky Institute of Geochemistry and Analytical Chemistry of Russian Academy of Sciences, Moscow, Russian Federation)

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This study focuses on the sorption behavior of oxidized multilayer graphene to actinides and rare earth elements in nitric acid solutions, and optimizes the conditions for obtaining new sorption materials. The efficiency of the obtained materials in solid-phase isolation and separation of actinides and REEs from nitric acid solutions is confirmed.
The removal of actinides and rare earth elements (REEs) in nitric acid solutions; produced in nuclear processes; is a challenging job. The present article describes the sorption behavior of oxidized multilayer graphene (o-MG) to actinides and rare earth elements (REEs) in nitric acid solutions (up to 3 mol L-1 HNO3), including nitrogen and phosphorus-containing reagents. The conditions for obtaining new sorption materials in a compact form; by adding directly a reagent (organic ligand) and a suspension of o-MG to nitric acid solutions; were optimized. o-MG was modified by using tetraoctyldiglycolamide, diphenyl-dibutylcarbamoyl-methyl-phosphine oxide, tri-octyl-phosphinoxide, di-(2-ethylhexyl) phosphoric acid, tributyl phosphate and di-2-ethyl-hexyl-methyl-phosphonate reagents were used. The formation time of the solid-phase extractants compact phase was 20-240 min. The new materials sorption capacity to U (VI), Th (IV), Pu (IV), La (III), Ce (III) and Eu (III) in nitric acid solutions (3 mol L-1 HNO3) was determined. The elements distribution coefficients were K-d similar to 10(3)-10(4) mL g(-1). The efficiency of the obtained materials was confirmed by the data on the solid-phase isolation and separation of actinides and REEs from nitric acid solutions (3 mol L-1 HNO3) in the presence of macro components (Cs, Sr, Fe, Mo, Pd, Zr, Co), which can be formed during recycling processes of spent nuclear materials and components used in nuclear medicine. (C) 2021 Elsevier B.V. All rights reserved.

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