Hostname: page-component-669899f699-8p65j Total loading time: 0 Render date: 2025-04-24T20:39:21.700Z Has data issue: false hasContentIssue false
  • English
  • Français

Alteration of Nuclear Waste Glass by Hydration

Published online by Cambridge University Press:  21 February 2011

John K. Bates  and
Martin J. Steindler
John K. Bates
Affiliation:
Argonne National Laboratory, Argonne, Illinois, USA
Martin J. Steindler
Affiliation:
Argonne National Laboratory, Argonne, Illinois, USA
Get access

Abstract

Aging of simulated nuclear waste glass by contact with a humid atmosphere results in the formation of a double hydration layer penetrating into the glass and in the formation of alteration products on the glass surface. This hydration process has been studied as a function of time, temperature, glass composition and water vapor pressure. A dual stage hydration rate was observed and rate constants were determined at each temperature. An Arrhenius plot for the initial stage alteration rate indicates the reaction mechanism does not change between the temperature limits of the experiment (120-240°C). This conclusion is supported by the sequence of mineral formation on the surface. This hydration process provides a means of accelerating aging reactions while simulating conditions that may exist in a nuclear waste repository.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 15: Symposium D – Scientific Basis for Nuclear Waste Management VI , 1982 , 83
Copyright
Copyright © Materials Research Society 1983

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.)

Article purchase

Temporarily unavailable

References

REFERENCES

1. Mendel, J. E. et al. , Report PNL-3802 (1981).Google Scholar
2. Altenhein, F. K., Lutze, W., and Malow, G., in Scientific Basis for Nuclear Waste Mangement, Moore, J. G., Ed., Plenum, NY, 3, 363 (1980).Google Scholar
3. Ericson, J. E., in Scientific Basis for Nuclear Waste Mangement, Moore, J. G., Ed., Plenum, NY, 3, 282 (1980).Google Scholar
4. Allen, C. C., in Scientific Basis for Nuclear Waste Mangement, 5, (1982) in press.Google Scholar
5. Seitz, M. G., Repository-Analog Experiments on Nuclear Waste Leaching and Migration, presented at the Int. Symp. on Migration in the Terrestrial Environment of Long-Lived Radionuclides from the Nuclear Fuel Cycle, Knoxville, TN, July 1981.Google Scholar
6. Winograd, J. J., Science 212, 1457 (1982).CrossRefGoogle Scholar
7. Bates, J. K., Jardine, L. J., and Steindler, M. J., Report ANL-82-11 (1982).Google Scholar
8. Steindler, M. J. et al. , Argonne National Laboratory, Chemical Engineering Division Fuel Cycle Programs Quarterly Progress Report, July-September 1982.CrossRefGoogle Scholar
9. Mendel, J. E., Nuclear Waste Materials Handbook, DOE/TIC 11400 (1981).Google Scholar