DEVELOPMENT OF AN IMPROVED SODIUM TITANATE FOR THE PRETREATMENT OF HIGH LEVEL NUCLEAR WASTE AT THE SAVANNAH RIVER SITE [electronic resource].
- Washington, D.C. : United States. Dept. of Energy, 2005. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Additional Creators:
- United States. Department of Energy. Savannah River Site, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove ¹³⁷Cs, ⁹°Sr and alpha-emitting radionuclides (i.e., actinides) prior to disposal onsite as low level waste. Separation processes planned at SRS include caustic side solvent extraction, for ¹³⁷Cs removal, and sorption of ⁹°Sr and alpha-emitting radionuclides onto monosodium titanate (MST). The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes ²³⁸Pu, ²³⁹Pu and ²⁴°Pu. This paper describes recent results to produce an improved sodium titanate material that exhibits increased removal kinetics and capacity for ⁹°Sr and alpha-emitting radionuclides compared to the baseline MST material.
- Published through SciTech Connect., 11/22/2005., "wsrc-ms-2005-00477", and Barnes, M. J.; Nyman, M. D.; Poirier, M. R.; Stallings, M. E.; Hobbs D. T.
- Funding Information:
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