Hostname: page-component-cd9895bd7-jn8rn Total loading time: 0 Render date: 2024-12-27T01:46:32.215Z Has data issue: false hasContentIssue false
  • English
  • Français

Detailed Processes of Surface Layer Formation in Borosilicate Waste Glass Dissolution

Published online by Cambridge University Press:  26 February 2011

John F. Flintoff  and
Alan B. Harker
John F. Flintoff
Affiliation:
Rockwell International Science Center, P.O. Box 1085 1049 Camino Dos Rios, Thousand Oaks, CA. 91360, USA
Alan B. Harker
Affiliation:
Rockwell International Science Center, P.O. Box 1085 1049 Camino Dos Rios, Thousand Oaks, CA. 91360, USA
Get access

Abstract

The morphology and chemical structure of surface layers formed during the aqueous leaching of the SRP-type borosilicate waste glass in simulated ground waters have been studied by SEM/EDXS, XRD, and surface spectroscopy. Comparison of layers formed in deionized, silicate, and brine waters shows the processes of both corrosion and precipitation to be highly localized. The corrosion process proceeds on the glass surface preferentially at points of stress and inhomogeneity. Crystalline and noncrystalline precipitates form in well-defined regions within the surface layers indicating the layer development process to be dominated by species migration and local saturation effects.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 44: Symposium N – Scientific Basis for Nuclear Waste Management VIII , 1984 , 147
Copyright
Copyright © Materials Research Society 1985

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

1. Final Report of the Defense High-Level Waste Leaching Mechanisms Program, edited by Mendel, J. E., Report PNL-5157, Battelle Pacific Northwest Laboratory, Richland, Washington (1984).Google Scholar
2. Harker, A.B. and Flintoff, J.F., “The Formation of Surface Layers and Reaction Products in the Leaching of Defense Borosilicate Nuclear Waste Glass,” submitted Nuclear Technology (1984).Google Scholar
3. Ringwood, A.E. and Willis, P.E., “Stress Corrosion Cracking in Borosilicate Glass from the Savannah River Plant,” Materials Research Society Annual Meeting 1983, Boston, Mass. (Abs.).Google Scholar
4. Mendel, J.E., “Nuclear Waste Materials Handbook,” Report DOE/TIC-11400, Battelle Pacific Northwest Laboratories, Richland, Washington (1981).Google Scholar
5. Jantzen, C.M., “Methods of Simulating Low Redox Potential (Eh) For a Basalt Repository,” Mat. Res. Soc. Symp. Proc. 26, edited by McVay, G.L. (North-Holland, N.Y., 1984), 613–622.Google Scholar
6. Jantzen, C.M., “Effects of Eh (Oxidation Potential) On Borosilicate Waste Glass Durability,” Advances In Ceramics Vol.8, edited by Wicks, G.G. and Ross, W.A. (The American Ceramic Society, Columbus, OH, 1984), 385–393.Google Scholar
7. Jantzen, C.M., Clarke, D.R., Morgan, P.E.D., and Harker, A.B., “Leaching of Polyphase Nuclear Waste Ceramics: Microstructural and Phase Characterization,” J. Am. Ceram. Soc. 65 (6),292–300 (1982).CrossRefGoogle Scholar
8. Ford, W.E., Dana's Textbook of Mineralogy 4th Edition (J. Wiley and Sons Inc., N.Y., 1949).Google Scholar