Uptake of radionuclides on microporous and layered ion exchange materials

Al-Attar, L; Dyer, A; Harjula, R

Abstract

Titanosilicates, layered manganese oxides and an antimonysilicate were tested for their ability to take up the
reprocessing spent fuel transuranium isotopes americium-241 and plutonium-236. This was performed in
different concentrations of acid, and sodium and calcium nitrate solutions to represent the conditions of
nuclear waste treatment. The purpose was to assess the waste types (acidic or low-medium-high-salt) most
suited to treatment by these materials. The experiments were carried out by the batch method and the results
obtained expressed as distribution coefficients. Variation in the magnitude and mechanism of actinide sorption
by the materials was attributed to the differences in the frameworks, physical properties (porosity, crystal size
and chemical composition) and surface charges of the ion exchangers. In nitric acid solutions, the Hantimonysilicate
proved to be a better sorbent than H-birnessite for both actinide elements. The void space
of AM-4 layered titanosilicate material made it appropriate for actinide removal in sodium salt solutions.
The differences in selectivity of Ca-antimonysilicate and Ca-birnessite for americium-241 and plutonium-
236 in 0.01 M calcium nitrate solution reflected the preference of each material for actinides over calcium
ions.

Citation

Al-Attar, L., Dyer, A., & Harjula, R. (2003). Uptake of radionuclides on microporous and layered ion exchange materials. Journal of Materials Chemistry, 13(12), 2963-2968. https://doi.org/10.1039/b308200h

• Journal Article Type: Article
• Publication Date: Sep 19, 2003
• Deposit Date: Sep 3, 2007
• Journal: Journal of Materials Chemistry
• Print ISSN: 0959-9428
• Publisher: Royal Society of Chemistry
• Peer Reviewed: Peer Reviewed
• Volume: 13
• Issue: 12
• Pages: 2963-2968
• DOI: https://doi.org/10.1039/b308200h
• Publisher URL: http://www.rsc.org/publishing/journals/JM/article.asp?doi=b308200h