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Leach Rates of High Activity Waste from Borosilicate Glass

John R. Wiley

Nuclear Technology / Volume 43 / Number 2 / April 1979 / Pages 268-272

Technical Paper / The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle / dx.doi.org/10.13182/NT79-A16317

Borosilicate glasses containing actual high-level Savannah River Plant waste were leached in static, distilled water. Leach rates based on 90Sr, 137Cs, and plutonium analyses were similar: 10−5 to 10−6 g of glass/(cm2·day) initially, 10−7 to 10−8 g/(cm2·day) after two weeks, and 10−8 to 10−9 g/(cm2·day) after 100 days. The leach rates were not directly correlated with waste composition, but were qualitatively related to the tendency of the glass to devitrify that could be caused by certain combinations of waste components. According to a proposed model, leach rates were diffusion-controlled during the entire 100-day test.