Containment of nuclear waste

Details Containment of nuclear waste Containment of nuclear waste

1980-06-25

1983-03-08

Kyle, Deborah L.

Compositions

Radioactive compositions

501 12, G21F 916

Patent

active

043760708

ABSTRACT:
Disclosed is a method of immobilizing nuclear waste in glass. A composition is prepared of about 30 to about 85% of a hydrolyzed glass-forming silicon compound, about 5 to about 30% of a glass-forming sodium compound, up to about 30% of a glass-forming aluminum compound, and about 5 to about 30% of a glass-forming boron, calcium, or magnesium compound. Up to an equal amount of nuclear waste is mixed into the composition and the mixture is heated at up to 500.degree. C. until dry. The mixture is then melted at 800.degree. to 1300.degree. C., and can be poured into ingots and cooled. The mixture can also be melted in situ with a laser.

REFERENCES:
patent: 3597252 (1971-08-01), Schroder et al.
patent: 3759683 (1973-09-01), Dislich et al.
Brezneva et al, "Vitrification of High Sodium-Aluminum Wastes", In: McCarthy, Ed, Scientific Basis for Nuclear Waste Mgmt., Plenum Press, New York, 1979, pp. 43-50.
Lutze et al., "Characterization of Glass and Glass-Ceramic Waste Forms,"In:McCarthy, Ed., Scientific Basis for Nuclear Waste Mgmt., Plenum Press, New York, 1979, pp. 69-81.

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