4.8 Article

Efficient Removal and Recovery of Uranium by a Layered Organic-Inorganic Hybrid Thiostannate

期刊

JOURNAL OF THE AMERICAN CHEMICAL SOCIETY
卷 138, 期 38, 页码 12578-12585

出版社

AMER CHEMICAL SOC
DOI: 10.1021/jacs.6b07351

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资金

  1. National Science Foundation of the United States [DMR-1410169]
  2. National Science Foundations of China [21373223, 21521061]
  3. 973 programs [2014CB845603, 2012CB821702]
  4. Haixi Institute of Chinese Academy of Sciences [CMZX-2014-001]

向作者/读者索取更多资源

Uranium is important in the nuclear fuel cycle both as an energy source and as radioactive waste. It is of vital importance to recover uranium from nuclear waste solutions for further treatment and disposal. Herein we present the first chalcogenide example, (Me2NH2)(1.33)(Me3NH)(0.67)Sn3S7 center dot 1.25H(2)O (FJSM-SnS), in which organic amine cations can be used for selective UO22+-ion-exchange. The UO22+-exchange kinetics perfectly conforms to pseudo-second-order reaction, which is observed for the first time in a chalcogenide ion-exchanger. This reveals the chemical adsorption process and its ion-exchange mechanism. FJSM-SnS has excellent pH stability in both strongly acidic and basic environments (pH = 2.1-11), with a maximum uranium-exchange capacity of 338.43 mg/g. It can efficiently capture UO22+ ions in the presence of high concentrations of Na+, Ca2+, or HCO3- (the highest distribution coefficient K-d value reached 4.28 X 10(4) mL/g). The material is also very effective in removing of trace levels of U in the presence of excess Na+ (the relative amounts of U removed are close to 100%). The UO22+center dot center dot center dot S2- interactions are the basis for the high selectivity. Importantly, the uranyl ion in the exchanged products could be easily eluted with an environmentally friendly method, by treating the UO22+-laden materials with a concentrated KCl solution. These advantages coupled with the very high loading capacity, low cost, environmentally friendly nature, and facile synthesis make FJSM-SnS a new promising remediation material for removal of radioactive U from nuclear waste solutions.

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