DEVELOPMENT OF AN IMPROVED SODIUM TITANATE FOR THE PRETREATMENT OF HIGH LEVEL NUCLEAR WASTE AT THE SAVANNAH RIVER SITE

Conference · Tue Nov 22 04:00:00 EST 2005

OSTI ID:881462

T, Hobbs D; Poirier, M R; Barnes, M J; Stallings, M E; Nyman, M D

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

• Research Organization: Savannah River Site (SRS), Aiken, SC
• Sponsoring Organization: USDOE
• DOE Contract Number: AC09-96SR18500
• OSTI ID: 881462
• Report Number(s): WSRC-MS-2005-00477
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ACTINIDES
CAPACITY
KINETICS
LIQUID WASTES
PLUTONIUM ISOTOPES
RADIOACTIVE WASTES
RADIOISOTOPES
REMOVAL
REPROCESSING
SEPARATION PROCESSES
SODIUM
SOLVENT EXTRACTION
SORPTION
TITANATES