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Laboratory testing of LITCO glasses
Author(s) -
Adam J. Ellison,
S. F. Wolf,
Edgar C. Buck,
J.S. Luo,
N.L. Dietz,
J. K. Bates,
W. L. Ebert
Publication year - 1995
Language(s) - English
Resource type - Reports
DOI - 10.2172/80967
Subject(s) - corrosion , materials science , durability , radioactive waste , saturation (graph theory) , metallurgy , mineralogy , optical glass , composite material , chemistry , nuclear chemistry , mathematics , combinatorics
The purpose of this program is to measure, the intermediate and long-term durability of glasses developed by Lockheed Idaho Technology Co. (LITCO) for the immobilization of calcined radioactive wastes. The objective is to use accelerated corrosion tests as an aid in developing durable waste form compositions. This is a report of tests performed on two LITCO glass compositions, Formula 127 and Formula 532. The main avenue for release of radionuclides into the environment in a geologic repository is the reaction of a waste glass with ground water, which alters the glass and releases its components into solution. These stages in glass corrosion are analyzed by using accelerated laboratory tests in which the ratio of sample surface area to solution volume, SA/V, is varied. At low SA/V, the solution concentrations of glass corrosion products remain low and the reaction approaches the forward rate. At higher SA/V the solution approaches saturation levels for glass corrosion products. At very high SA/V the solution is rapidly saturated in glass corrosion products and secondary crystalline phases precipitate. Tests at very high SA/V provide information about the composition of the solution at saturation or, when no solution is recovered, the identities and the order of appearance of secondary crystalline phases. Tests were applied to Formula 127 and Formula 532 glasses to provide information about the interim and long-term stages in glass corrosion

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