Chemical durability of SRP waste glass: saturation effects and influence of SA/V
Conference
·
OSTI ID:6632181
The leachability of SRP waste glass is being assessed as a function of saturation effects, including solution pH and the ratio of glass surface area to volume of leachant (SA/V). The use of SA/V as a scaling factor for accelerated testing is also being assessed. Sample weight losses, pH changes, solution analyses, and surface studies were used to evaluate leachability in the present study and to provide better understanding of the corrosion mechanisms involved. Conclusions from this study are as follows: waste glass leach rates decrease significantly with increasing SA/V. Since high SA/V values are expected in geologic repositories, waste glass leachability in actual burial should be even lower than in laboratory tests performed at lower SA/V; at high SA/V, the rate of glass dissolution is reduced and limited by solution saturation effects; leaching of waste glass in buffered solutions of pH 3, 7, and 11 show that other factors, such as formation of surface layers, in addition to silica solution saturation, may contribute to decreasing the leach rate, depending on the conditions of the test; for intermediate SA/V ratios (1.0 cm/sup -1/), the leach rates of powders are similar to the leach rates of monolithic solids, based on Si and B extraction; and leaching at high SA/V for short periods of time is not always equivalent to leaching at low SA/V for longer times, i.e. SA/V may not be a scaling factor applicable to all elements. 5 references, 14 figures, 7 tables.
- Research Organization:
- Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab.
- DOE Contract Number:
- AC09-76SR00001
- OSTI ID:
- 6632181
- Report Number(s):
- DP-MS-84-37; CONF-840440-6; ON: DE84016348
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
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12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
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ACTINIDES
ALKALI METALS
ALKALINE EARTH METALS
ALUMINIUM
BORON
BOROSILICATE GLASS
CESIUM
DATA
DISSOLUTION
ELEMENTS
EXPERIMENTAL DATA
GLASS
HIGH-LEVEL RADIOACTIVE WASTES
HYDROGEN COMPOUNDS
INFORMATION
IRON
LEACHING
MAGNESIUM
MANGANESE
MATERIALS
METALS
NUMERICAL DATA
OXYGEN COMPOUNDS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
SATURATION
SEMIMETALS
SEPARATION PROCESSES
SILICON
SODIUM
STRONTIUM
SURFACE AREA
SURFACE PROPERTIES
TRANSITION ELEMENTS
URANIUM
VOLUME
WASTES
WATER
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
360605 -- Materials-- Radiation Effects
ACTINIDES
ALKALI METALS
ALKALINE EARTH METALS
ALUMINIUM
BORON
BOROSILICATE GLASS
CESIUM
DATA
DISSOLUTION
ELEMENTS
EXPERIMENTAL DATA
GLASS
HIGH-LEVEL RADIOACTIVE WASTES
HYDROGEN COMPOUNDS
INFORMATION
IRON
LEACHING
MAGNESIUM
MANGANESE
MATERIALS
METALS
NUMERICAL DATA
OXYGEN COMPOUNDS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
SATURATION
SEMIMETALS
SEPARATION PROCESSES
SILICON
SODIUM
STRONTIUM
SURFACE AREA
SURFACE PROPERTIES
TRANSITION ELEMENTS
URANIUM
VOLUME
WASTES
WATER