• 文献标题:   Preparation and characterization of oxidized graphene for actinides and rare earth elements removal in nitric acid solutions from nuclear wastes
  • 文献类型:   Article
  • 作  者:   ALI I, ZAKHARCHENKO EA, MYASOEDOVA GV, MOLOCHNIKOVA NP, RODIONOVA AA, BAULIN VE, BURAKOV AE, BURAKOVA IV, BABKIN AV, NESKOROMNAYA EA, MELEZHIK AV, TKACHEV AG, HABILA MA, ELMARGHANY A, SHEIKH M, GHFAR A
  • 作者关键词:   actinides rare earth element, nuclear waste, sorption, oxidized multilayer graphene, distribution coefficient
  • 出版物名称:   JOURNAL OF MOLECULAR LIQUIDS
  • ISSN:   0167-7322 EI 1873-3166
  • 通讯作者地址:  
  • 被引频次:   25
  • DOI:   10.1016/j.molliq.2021.116260 EA MAY 2021
  • 出版年:   2021

▎ 摘  要

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.