Graphene oxide for effective radionuclide removal

被引:330
|
作者
Romanchuk, Anna Yu [1 ]
Slesarev, Alexander S. [2 ]
Kalmykov, Stepan N. [1 ]
Kosynkin, Dmitry V. [2 ]
Tour, James M. [2 ,3 ]
机构
[1] Moscow MV Lomonosov State Univ, Dept Chem, Moscow 119991, Russia
[2] Rice Univ, Dept Chem, Houston, TX 77005 USA
[3] Rice Univ, Dept Mech Engn & Mat Sci, Houston, TX 77005 USA
关键词
REDUCTION; DISPERSIONS; NANOSHEETS;
D O I
10.1039/c2cp44593j
中图分类号
O64 [物理化学(理论化学)、化学物理学];
学科分类号
070304 ; 081704 ;
摘要
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.
引用
收藏
页码:2321 / 2327
页数:7
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