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Title: Immobilization of sulfate-containing wastes in borosilicate glass using fluoride additives

Journal Article · · Atomic Energy (New York)
DOI:https://doi.org/10.1007/BF02408200· OSTI ID:115168

The choice of borosilicate glasses as a matrix for immobilizing radioactive wastes is largely justified by the properties of the final vitrified product to be stored for a long time: High chemical, thermal, and radiation resistance. The structure of borosilicate glasses makes it possible to use them as a matrix for high and medium level wastes of diverse chemical composition. However, individual components of the wastes - sulfate, chloride, and molybdate-containing components - have a limited solubility in borosilicate glasses. This results in phase separation (stable liquation) in the vitrification process and decreases the quality of the vitrified product.

Sponsoring Organization:
USDOE
OSTI ID:
115168
Journal Information:
Atomic Energy (New York), Vol. 76, Issue 3; Other Information: PBD: Sep 1994; TN: Translated from Atomnaya Energiya; 76: No. 3, 234-237(Mar 1994)
Country of Publication:
United States
Language:
English