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Issue 10, 2016
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Removal of TcO4 ions from solution: materials and future outlook

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Abstract

Technetium mainly forms during artificial nuclear fission; it exists primarily as TcO4 in nuclear waste, and it is among the most hazardous radiation-derived contaminants because of its long half-life (t1/2 = 2.13 × 105 years) and environmental mobility. The high water solubility of TcO4 (11.3 mol L−1 at 20 °C) and its ability to readily migrate within the upper layer of the Earth's crust make it particularly hazardous. Several types of materials, namely resins, molecular complexes, layered double hydroxides, and pure inorganic and metal–organic materials, have been shown to be capable of capturing TcO4 (or other oxoanions) from solution. In this review, we give a brief description about the types of materials that have been used to capture TcO4 and closely related oxyanions so far and discuss the possibility of using metal–organic frameworks (MOFs) as next-generation ion-exchange materials for the stated application. In particular, with the advent of ultra-stable MOF materials, in conjunction with their chemical tunability, MOFs can be applied to capture these oxyanions under real-life conditions.

Graphical abstract: Removal of TcO4− ions from solution: materials and future outlook

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Publication details

The article was received on 23 Nov 2015 and first published on 07 Mar 2016


Article type: Tutorial Review
DOI: 10.1039/C5CS00330J
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Chem. Soc. Rev., 2016,45, 2724-2739

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    Removal of TcO4 ions from solution: materials and future outlook

    D. Banerjee, D. Kim, M. J. Schweiger, A. A. Kruger and P. K. Thallapally, Chem. Soc. Rev., 2016, 45, 2724
    DOI: 10.1039/C5CS00330J

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