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European Journal of Mineralogy; September, October 2000; v. 12; no. 5; p. 999-1014; DOI: 10.1127/0935-1221/2000/0012-0999
© 2000 E. Schweizerbart'sche Verlagsbuchhandlung Science Publishers
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Articles

Experimental Cs and Sr sorption on analcime in rock-buffered systems at 250–300°C and Psat and the thermodynamic evaluation of mineral solubilities and phase relations

Alexander F. REDKIN1,* and John J. HEMLEY2

1 Institute of Experimental Mineralogy, Russian Academy of Sciences, Chernogolovka, Moscow District 142432, Russia
2 U.S. Geological Survey, 954 National Center, Reston, VA 22092, USA

* e-mail: redkin{at}iem.ac.ru

Experimental studies on replacement of Na by Cs and Sr in analcime-albite bearing buffered assemblages were carried out at 250–300°C and Psat = 39.7-85.8 bars in pure water and in chloride solution. This investigation shows that such ion exchange of Na for Cs and Sr in analcime changes the Si/Al ratio. The compositions of end members for Cs and Sr analcimes at 250°C are shown to be Cs0.95Al0.79Si2.17O6 and Sr0.645Al1.41Si1.62O6. Continuous solid solutions between Cs and Na and Sr and Na do not appear to exist.

Based on the composition of the aqueous chloride solutions, the thermodynamic properties of Cs, Sr and Na analcimes were determined and used in thermodynamic simulations in Cs and Sr leaching from albite-(Cs, Sr, Na) analcime assemblages at 250°C. In line with the above, the minimum leachability of Cs and Sr from Cs- and Sr-bearing analcimes occurs at pH values above 8 with an analcime-albite-paragonite buffer. The analcime-albite-paragonite assemblage can, therefore, act as a potential sorption barrier to the migration of Cs and Sr from radionuclide contaminated materials owing to the insolubility of Cs and Sr bearing analcimes. These findings have implications for underground High Level Waste storage facilities designed for maximum safety at moderately elevated temperatures.

Key-words: analcimes, pollucite, buffered systems, sorption, solid solutions, solubility, thermodynamic properties, nuclear waste storage.




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JOURNAL HOME HELP FEEDBACK/COMMNET SUBSCRIBE ARCHIVE SEARCH TABLE OF CONTENTS
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