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Sodium Diffusion and Leaching of Simulated Nuclear Waste Glass
Author(s) -
McGRAIL B. P.,
KUMAR A.,
DAY D. E.
Publication year - 1984
Publication title -
journal of the american ceramic society
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.9
H-Index - 196
eISSN - 1551-2916
pISSN - 0002-7820
DOI - 10.1111/j.1151-2916.1984.tb19635.x
Subject(s) - borosilicate glass , leaching (pedology) , diffusion , radioactive waste , sodium , materials science , analytical chemistry (journal) , mineralogy , chemistry , metallurgy , nuclear chemistry , thermodynamics , soil science , environmental chemistry , geology , soil water , physics
Oxides such as CaO, ZnO, Fe 2 0O 3 , and Zr0O 2 were substituted for Si0O 2 into a 14 Na 2 0‐10 B 2 0O 3 ‐76 Si0O 2 (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.

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