Sodium Diffusion and Leaching of Simulated Nuclear Waste Glass
Oxides such as CaO, ZnO, Fe20O3, and Zr0O2 were substituted for Si0O2 into a 14 Na20-10 B20O3-76 Si0O2 (wt%) glass in proportion to their weight percent in PNL-7668 simulated nuclear waste glass. No correlation was found between the Na diffusion coefficient (DNa) in the bulk glass and sodium leaching in water for any of the iron-containing borosilicate glasses. Effective diffusion coefficients calculated from the sodium leach rates in deionized water were 500 to 2000 times larger than DNa. The experimental leaching data agreed with a diffusion-convection model where the convective term was a measured “phase-boundary”velocity moving into the glass.
B. P. McGrail et al., "Sodium Diffusion and Leaching of Simulated Nuclear Waste Glass," Journal of the American Ceramic Society, vol. 67, no. 7, pp. 463-467, Wiley, Jul 1984.
The definitive version is available at https://doi.org/10.1111/j.1151-2916.1984.tb19635.x
Nuclear Engineering and Radiation Science
Materials Science and Engineering
Keywords and Phrases
Glass - Radiation Effects; Borosilicate Glass; Nuclear Waste Disposal; Radioactive Waste; Radioactive Materials
International Standard Serial Number (ISSN)
Article - Journal
© 1984 Wiley, All rights reserved.
01 Jul 1984