Corrosion of simulated nuclear waste glass
作者： S Musić , M Ristić , M Gotić , J Forić , None
DOI: 10.1007/BF02037168
关键词: High-level waste 、 Materials science 、 Nuclear chemistry 、 Radioactive waste 、 Borosilicate glass 、 Leaching (metallurgy) 、 Chemical composition 、 Waste treatment 、 Vitrification 、 Metallurgy 、 Corrosion
摘要: Glasses are suitable host matrices for the immobilization of high-level radioactive wastes. The corrosion behaviour nuclear waste glass in water is considerable importance, since a potential route returning radionuclides to biosphere their leaching from form into groundwater and subsequent transport by surface. In this study, preparation characterization borosilicate glasses different chemical composition were investigated. Borosilicate doped with simulated oxides. these was followed measuring leach rates (g·cm−2·day−1), as function time. It found that (weight %), 15.61% Na2O, 10.39% B2O3, 45.31% SiO2, 13.42% ZnO, 6.61% TiO2 8.66% oxides, characterized low melting temperature good resistance water. Influence passive layers on discussed.
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