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Surface Characterization of Simulated Low-Level Radioactive Waste Glasses Corroded in Water and LiOH Buffer Solution

Published online by Cambridge University Press:  15 February 2011

H. Li ,
M. J. Schweiger ,
P. Hrma  and
X Feng
H. Li
Affiliation:
Pacific Northwest National Laboratory, Box 999, P8–37, Richland, WA 99352
M. J. Schweiger
Affiliation:
Pacific Northwest National Laboratory, Box 999, P8–37, Richland, WA 99352
P. Hrma
Affiliation:
Pacific Northwest National Laboratory, Box 999, P8–37, Richland, WA 99352
X Feng
Affiliation:
Pacific Northwest National Laboratory, Box 999, P8–37, Richland, WA 99352
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Abstract

Chemical durability of simulated radioactive low-level waste (LLW) baseline glass, 6- 5412, was found to decrease with the addition of either phosphate or sulfate, or chromium oxide. Scanning electron microscopic study of corroded samples suggests that the effect of these components on glass chemical durability may be attributed to cluster formation of: Na-O-P-O or Na-O-S-O, or (O0)3-Cr3+(O−)3 groups. Preferential corrosion attack was severe on certain corroded sample surface areas that are possibly enriched in these clusters. Durability tests in a solution with LiOH as a buffer suggest that chlorine in the glass slightly improved glass corrosion resistance, while fluorine significantly deteriorated glass corrosion resistance.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 412: Symposium V – Scientific Basis for Nuclear Waste Management XIX , 1995 , 213
Copyright
Copyright © Materials Research Society 1996

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