Development of an improved sodium titanate for the pretreatment of nuclear waste at the Savannah River Site
- Savannah River National Laboratory, Westinghouse Savannah River Company, Aiken, SC (United States)
- Sandia National Laboratories, Albuquerque, NM (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 sorption of Sr-90 and alpha-emitting radionuclides onto monosodium titanate (MST) and caustic side solvent extraction, for Cs-137 removal. The MST and separated Cs-137 will be encapsulated into a borosilicate glass wasteform for eventual entombment at the federal repository. 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, 1628 E. Southern Avenue, Suite 9 - 332, Tempe, AZ 85282 (United States)
- OSTI ID:
- 21326140
- Report Number(s):
- INIS-US-10-WM-08374; TRN: US10V0570067505
- Resource Relation:
- Conference: WM'08: Waste Management Symposium 2008 - HLW, TRU, LLW/ILW, Mixed, Hazardous Wastes and Environmental Management - Phoenix Rising: Moving Forward in Waste Management, Phoenix, AZ (United States), 24-28 Feb 2008; Other Information: Country of input: France; 9 refs
- Country of Publication:
- United States
- Language:
- English
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DEVELOPMENT OF AN IMPROVED TITANATE-BASED SORBENT FOR STRONTIUM AND ACTINIDE SEPARATIONS UNDER STRONGLY ALKALINE CONDITIONS
Development of an Improved Sodium Titanate for the Pretreatment of Nuclear Waste at the Savannah River Site
Related Subjects
ACTINIDES
ALPHA-BEARING WASTES
BOROSILICATE GLASS
CESIUM 137
HIGH-LEVEL RADIOACTIVE WASTES
KINETICS
LIQUID WASTES
LOW-LEVEL RADIOACTIVE WASTES
PLUTONIUM 238
PLUTONIUM 239
PLUTONIUM 240
REPROCESSING
SAVANNAH RIVER PLANT
SODIUM
SODIUM COMPOUNDS
SOLVENT EXTRACTION
STRONTIUM 90
TITANATES
VITRIFICATION
WASTE FORMS