The effects of surface area to solution volume on waste glass leaching
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:6319129
Silicon solubility limitations appear to control the rate of corrosion of a complex simulated nuclear waste glass at relatively high values of the glass surface area to solution volume ratio (SA/V). Undersaturated glass components such as sodium and boron were affected by SA/V in a manner similar to silicon. Under relatively low SA/V conditions, glass corrosion was unaffected by changes in the SA/V ratio. Congruent dissolution was never observed, in contrast to previous results for simple and certain complex silicate glasses. Increases in the SA/V value may be a viable method for performing accelerated leach resistance testing of nuclear waste forms.
- Research Organization:
- Pacific Northwest Laboratory, Richland, Washington
- OSTI ID:
- 6319129
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 62:2; ISSN NUTYB
- 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
360604 -- Materials-- Corrosion
Erosion
& Degradation
CHEMICAL REACTIONS
CORROSION
DISSOLUTION
ELEMENTS
GLASS
LEACHING
SEMIMETALS
SEPARATION PROCESSES
SILICON
SURFACE AREA
SURFACE PROPERTIES
TESTING
WASTE FORMS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
360604 -- Materials-- Corrosion
Erosion
& Degradation
CHEMICAL REACTIONS
CORROSION
DISSOLUTION
ELEMENTS
GLASS
LEACHING
SEMIMETALS
SEPARATION PROCESSES
SILICON
SURFACE AREA
SURFACE PROPERTIES
TESTING
WASTE FORMS