4.6 Article

Graphene oxide for effective radionuclide removal

期刊

PHYSICAL CHEMISTRY CHEMICAL PHYSICS
卷 15, 期 7, 页码 2321-2327

出版社

ROYAL SOC CHEMISTRY
DOI: 10.1039/c2cp44593j

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资金

  1. ONR MURI program [00006766, N00014-09-1-1066]
  2. M-I SWACO
  3. AFOSR [FA9550-09-1-0581]
  4. Ministry of Education and Science of Russian Federation [11.519.11.5011]
  5. RF President stipendium [SP-173.2012.2]
  6. Russian Basic Research Foundation [12-03-31370]

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Here we show the efficacy of graphene oxide (GO) for rapid removal of some of the most toxic and radioactive long-lived human-made radionuclides from contaminated water, even from acidic solutions (pH < 2). The interaction of GO with actinides including Am(III), Th(IV), Pu(IV), Np(V), U(VI) and typical fission products Sr(II), Eu(III) and Tc(VII) were studied, along with their sorption kinetics. Cation/GO coagulation occurs with the formation of nanoparticle aggregates of GO sheets, facilitating their removal. GO is far more effective in removal of transuranium elements from simulated nuclear waste solutions than other routinely used sorbents such as bentonite clays and activated carbon. These results point toward a simple methodology to mollify the severity of nuclear waste contamination, thereby leading to effective measures for environmental remediation.

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