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Title: Removal of TcO 4 - ions from solution: materials and future outlook

Journal Article · · Chemical Society Reviews
DOI:https://doi.org/10.1039/c5cs00330j· OSTI ID:1337210
 [1];  [1];  [1];  [2];  [1]
  1. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
  2. USDOE Office of River Protection, Richland, WA (United States)

Technetium mainly forms during artificial nuclear fission; it exists primarily as TcO4- in the nuclear waste, and is among the most hazardous radiation-derived contaminants because of its long half-life (t1/2 = 2.13 × 105 yrs) 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 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.

Research Organization:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Organization:
USDOE Office of Environmental Management (EM)
DOE Contract Number:
AC05-76RL01830
OSTI ID:
1337210
Report Number(s):
PNNL-SA-117349; CSRVBR; 830403000
Journal Information:
Chemical Society Reviews, Vol. 45, Issue 10; ISSN 0306-0012
Publisher:
Royal Society of Chemistry
Country of Publication:
United States
Language:
English

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