Development of an Improved Sodium Titanate for the Pretreatment of Nuclear Waste at the Savannah River Site

Conference · Sat Jul 01 00:00:00 EDT 2006

OSTI ID:21208600

Hobbs, D T; Poirier, M R; Barnes, M J; Stallings, M E; Fink, S D ^[1]; Nyman, M D ^[2]

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1. Savannah River National Laboratory, Westinghouse Savannah River Company, Aiken, SC 29808 (United States)
2. Sandia National Laboratories, Albuquerque, NM 87185 (United States)

High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove Cs-137, Sr-90 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 {sup 137}Cs removal, and sorption of Sr-90 and alpha-emitting radionuclides onto monosodium titanate (MST). The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes Pu-238, Pu-239 and Pu-240. This paper describes recent results to produce an improved sodium titanate material that exhibits increased removal kinetics and capacity for Sr-90 and alpha-emitting radionuclides compared to the baseline MST material. (authors)

• Research Organization: WM Symposia, Inc., PO Box 13023, Tucson, AZ, 85732-3023 (United States)
• OSTI ID: 21208600
• Report Number(s): INIS-US-09-WM-06093; TRN: US09V0911079387
• Resource Relation: Conference: Waste Management 2006 Symposium - WM'06 - Global Accomplishments in Environmental and Radioactive Waste Management: Education and Opportunity for the Next Generation of Waste Management Professionals, Tucson, AZ (United States), 26 Feb - 2 Mar 2006; Other Information: Country of input: France; 8 refs
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ACTINIDES
CESIUM 137
HIGH-LEVEL RADIOACTIVE WASTES
KINETICS
LIQUID WASTES
LOW-LEVEL RADIOACTIVE WASTES
PLUTONIUM 238
PLUTONIUM 239
PLUTONIUM 240
REMOVAL
REPROCESSING
SAVANNAH RIVER PLANT
SODIUM COMPOUNDS
SOLVENT EXTRACTION
SORPTION
STRONTIUM 90
TITANATES