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Simulation of the Waste Glass Behavior in a Loamy Soil of the Wet Repository Site
Published online by Cambridge University Press: 21 March 2011
Abstract
A model developed for description of waste glass corrosion has been applied to assess the radionuclide release from real radioactive (intermediate level) vitrified material over extended storage periods. Field data generated during the long-term testing of the prototype waste glass packages were mathematically processed and the derived parameters used in model calculations. Regardless of the corrosive saturated conditions of the wet near-surface repository, the fairly high safety of trench disposal has been demonstrated for borosilicate glass containing real NPP- operational waste.
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- Copyright © Materials Research Society 2001
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