Sodium Diffusion and Leaching of Simulated Nuclear Waste Glass

Author

B. P. McGrail
Arvind S. Kumar, Missouri University of Science and TechnologyFollow
D. E. Day, Missouri University of Science and TechnologyFollow

Abstract

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 (D_Na) 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 D_Na. The experimental leaching data agreed with a diffusion-convection model where the convective term was a measured “phase-boundary”velocity moving into the glass.

Recommended Citation

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

Department(s)

Nuclear Engineering and Radiation Science

Second Department

Materials Science and Engineering

Keywords and Phrases

Glass - Radiation Effects; Borosilicate Glass; Nuclear Waste Disposal; Radioactive Waste; Radioactive Materials

International Standard Serial Number (ISSN)

0002-7820

Document Type

Article - Journal

Document Version

Citation

File Type

text

Language(s)

English

Rights

© 1984 Wiley, All rights reserved.

Publication Date

01 Jul 1984