Nuclear Waste Glass Durability: I, Predicting Environmental Response from Thermodynamic (Pourbaix) Diagrams
Conference
·
· Journal of the American Ceramic Society
- Du Pont de Nemours (E.I.) and Co., Aiken, SC (United States). Savannah River Lab.
Pourbaix diagrams are shown to conceptually explain dissolution of glasses in terms of their thermodynamic stability and surface layer formation. To predict the long-term effects of ground-water contact on the durability of nuclear waste glass in a geologic repository, the nature of the glass dissolution process has been extensively examined. Hydration thermodynamics has been used to quantify the role of glass composition and the effect of solution pH. The glass compositions examined vary widely in composition and include natural, lunar, medieval, and nuclear waste glasses, as well as some glass-ceramics. The known effects of solution pH and oxidation potential (Eh) on glass dissolution are empirically described by thermodynamically calculated Pourbaix diagrams. Statistical analysis of over 300 glass durability tests demonstrates that the Pourbaix diagram can be quantified because of (1) the colinearity of the hydration free energy with solution pH defined by the Nernst equation and (2) the colinearity of the solution pH with the concentration of dissolved silicon and boron in the solution defined by the pH dependence of the ion activities. Construction of Pourbaix diagrams to describe glass dissolution serves to unify and categorize various existing experimental glass dissolution data.
- Research Organization:
- Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab.
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC09-89SR18035; AC09-76SR00001
- OSTI ID:
- 6171408
- Report Number(s):
- DP-MS--87-2-Rev.1; CONF-870422--14-Rev.1; ON: DE91009320
- Conference Information:
- Journal Name: Journal of the American Ceramic Society Journal Issue: 9 Journal Volume: 75
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
052002 -- Nuclear Fuels-- Waste Disposal & Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
360603 -- Materials-- Properties
360604* -- Materials-- Corrosion
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CHEMICAL ANALYSIS
CHEMICAL COMPOSITION
COMPUTERIZED SIMULATION
DISPERSIONS
DISSOLUTION
GLASS
GROUND WATER
HIGH-LEVEL RADIOACTIVE WASTES
HYDRATION
HYDROGEN COMPOUNDS
LEACHATES
MANAGEMENT
MATERIALS
MATHEMATICS
MIXTURES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PH VALUE
PHYSICAL PROPERTIES
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REDOX POTENTIAL
REGRESSION ANALYSIS
SIMULATION
SOLUTIONS
SOLVATION
STATISTICS
TESTING
THERMODYNAMIC PROPERTIES
UNDERGROUND DISPOSAL
VITRIFICATION
WASTE DISPOSAL
WASTE FORMS
WASTE MANAGEMENT
WASTES
WATER
WEATHERING
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
360603 -- Materials-- Properties
360604* -- Materials-- Corrosion
Erosion
& Degradation
CHEMICAL ANALYSIS
CHEMICAL COMPOSITION
COMPUTERIZED SIMULATION
DISPERSIONS
DISSOLUTION
GLASS
GROUND WATER
HIGH-LEVEL RADIOACTIVE WASTES
HYDRATION
HYDROGEN COMPOUNDS
LEACHATES
MANAGEMENT
MATERIALS
MATHEMATICS
MIXTURES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PH VALUE
PHYSICAL PROPERTIES
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REDOX POTENTIAL
REGRESSION ANALYSIS
SIMULATION
SOLUTIONS
SOLVATION
STATISTICS
TESTING
THERMODYNAMIC PROPERTIES
UNDERGROUND DISPOSAL
VITRIFICATION
WASTE DISPOSAL
WASTE FORMS
WASTE MANAGEMENT
WASTES
WATER
WEATHERING