Disposition of actinides released from high-level waste glass

Conference · Sat Dec 31 04:00:00 EST 1994

OSTI ID:39185

Ebert, W L; Bates, J K; Buck, E C; Gong, M; Wolf, S F ^[1]

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1. Argonne National Lab., IL (United States)

The disposition of actinide elements released from high-level waste glasses into a tuff groundwater in laboratory tests at 90{degrees}C at various glass surface area/leachant volume ratios (S/V) between dissolved, suspended, and sorbed fractions has been measured. While the maximum release of actinides is controlled by the corrosion rate of the glass matrix, their solubility and sorption behavior affects the amounts present in potentially mobile phases. Actinide solubilities are affected by the solution pH and the presence of complexants released from the glass, such as sulfate, phosphate, and chloride, radiolytic products, such as nitrate and nitrite, and carbonate. Sorption onto inorganic colloids formed during lass corrosion may increase the amounts of actinides in solution, although subsequent sedimentation of these colloids under static conditions leads to a significant reduction in the amount of actinides in solution. The solution chemistry and observed actinide behavior depend on the S/V of the test. Tests at high S/V lead to higher pH values, greater complexant concentrations, and generate colloids more quickly than tests at low S/V. The S/V also affects the rate of glass corrosion.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 39185
• Report Number(s): CONF-940416--
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
36 MATERIALS SCIENCE
ACTINIDES
CHEMICAL COMPOSITION
COLLOIDS
CORROSION
DISSOLUTION
GLASS
HIGH-LEVEL RADIOACTIVE WASTES
LEACHING
PHASE STABILITY
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTE STORAGE
SAVANNAH RIVER PLANT
SOLUBILITY
SORPTION
TUFF
VITRIFICATION
Yucca Mountain Project