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Title: Development of glass compositions for immobilization of SRP waste

Technical Report ·
DOI:https://doi.org/10.2172/6456251· OSTI ID:6456251

An improved composition of glass frit, termed 411, was developed for the immobilization of SRP high-level radioactive waste. In comparison with frit compositions previously studied, the new composition offers the following advantages: the amount of ferrite-spinel crystals formed is greatly decreased because the TiO/sub 2/ content is much lower; a higher lithium-to-sodium ratio decreases the viscosity of glass mixtures containing high-aluminum waste. The compositional studies leading to the development of the improved glass are reported.

Research Organization:
Du Pont de Nemours (E.I.) and Co., Aiken, SC (United States). Savannah River Lab.
DOE Contract Number:
EY-76-C-09-0001
OSTI ID:
6456251
Report Number(s):
DP-1517; TRN: 79-008914
Country of Publication:
United States
Language:
English

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Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
GLASS
CHEMICAL COMPOSITION
RADIOACTIVE WASTE PROCESSING
SOLIDIFICATION
BORON OXIDES
CALCIUM OXIDES
CRYSTALLIZATION
FERRITES
LITHIUM OXIDES
QUANTITY RATIO
SILICON OXIDES
SODIUM OXIDES
SPINELS
TITANIUM OXIDES
VISCOSITY
VITRIFICATION
ALKALI METAL COMPOUNDS
ALKALINE EARTH METAL COMPOUNDS
ALUMINIUM COMPOUNDS
ALUMINIUM OXIDES
BORON COMPOUNDS
CALCIUM COMPOUNDS
CHALCOGENIDES
FERRIMAGNETIC MATERIALS
IRON COMPOUNDS
LITHIUM COMPOUNDS
MAGNESIUM COMPOUNDS
MAGNESIUM OXIDES
MAGNETIC MATERIALS
MANAGEMENT
MINERALS
OXIDES
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PROCESSING
SILICON COMPOUNDS
SODIUM COMPOUNDS
TITANIUM COMPOUNDS
TRANSITION ELEMENT COMPOUNDS
WASTE MANAGEMENT
WASTE PROCESSING
052001* - Nuclear Fuels- Waste Processing