Published online by Cambridge University Press: 03 September 2012
The behaviour of waste glass was investigated under open site disposalconditions. This glass was produced by vitrification of intermediate levelradioactive waste from nuclear power plants. Two types of borosilicateglasses were obtained for two different reactor wastes, WWER and RBM.K.Leaching and alteration mechanisms are discussed as well as the dataprocessing technique used for these long term tests. The decay ofradionuclides was accounted for in order to obtain correct results. Theleaching factors obtained can be used for the assesment of radionuclideretention. Discontinuous leaching of Cs-137 has been observed during morethan 8 years testing time. The fluctuating leaching rate depends on glasscomposition. The average leaching rate remains within (0.4 – 4) μg/sq.sm·day.
Alteration of waste glass includes the formation of surface layers andcracks on the glass surface. SEM analysis of glass was used to show thesesurface layers. The thickness of the layers was determined to be within 2–6μm. The structure of these layers depends on glass composition and theinterfacing environment.