Hostname: page-component-7b7567c8c-2n9c9 Total loading time: 0 Render date: 2026-11-15T08:51:29.276Z Has data issue: false hasContentIssue false
  • English
  • Français

Control of Oxidation Potential for Basalt Repository Simulation Tests

Published online by Cambridge University Press:  26 February 2011

Carol M. Jantzen and
George G. Wicks
Carol M. Jantzen
Affiliation:
E. I. du Pont de Nemours and Company, Savannah River Laboratory, Aiken, South Carolina 29808
George G. Wicks
Affiliation:
E. I. du Pont de Nemours and Company, Savannah River Laboratory, Aiken, South Carolina 29808
Get access

Abstract

Borosilicate waste glass durability in simulated repository environments can be assessed by use of static tests in leach vessels fabricated of the representative geomedia. Control of the oxidation potential during the test simulates a basalt repository environment. Under very anoxic conditions (i.e. at negative Eh values), the interactions between basalt and SRP waste glass in silica-saturated basaltic groundwaters are the same as those of basalt and groundwater when no waste glass is present. The lack of significant leaching of ions from the waste glass and the lack of any significant changes in either the leached surfaces of glass or basalt under anoxic conditions suggests that the components of this system are at equilibrium when oxygen is absent.

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

1. Mendel, J. E., Sci. Basis for Nuclear Waste Management, VI, Elsevier, Publ. Co., New York, pp 1–7, 1983.Google Scholar
2. Jacobs, G. K. and Apted, M. J., EOS Trans. Amer. Geophys. Union, 62, p 1065, 1981.Google Scholar
3. Strachan, D. M., Sci. Basis for Nuclear Waste Management, V, Elsevier Publ. Co., New York, pp 181–191, 1982.Google Scholar
4. Mendel, J. E., Pacific Northwest Laboratory, Richland, WA, PNL-4382, p 255, 1982.Google Scholar
5. Jantzen, C.M., Advances in Ceramics, 8, Nuclear Waste Management, Am. Ceramic Soc, Columbus, OH, pp 385–397, 1984.Google Scholar
6. Jantzen, C.M., Sci. Basis for Nuclear Waste Management, VII, Elsevier Publ.Co., New York, pp 613–621, 1984.Google Scholar
7. Personal communication Smith, M. J., “Reference Grande Ronde Groundwater No. 4,” October 4, 1983.Google Scholar
8. Wicks, G. G., Bibler, N. E., Jantzen, C. M., and Plodinec, M. J., “Repository Simulation Tests,” Presented at 86th Annual Meeting of American Ceramic Society, Pittsburgh, PA, April 1984.CrossRefGoogle Scholar
9. Nuclear Waste Materials Handbook Waste Form Test Methods, MCC-IP Static Test, Prepared by Materials Characterization Center, Mendel, J. E., Manager, USDOE Report DOE/TIC-11400 Pacific Northwest Laboratory, Richland, WA, 1981.Google Scholar
10. Jantzen, C. M. and Plodinec, M. J., J. Non-Crystalline Solids, 67, [1–3], pp 207–223, 1984.CrossRefGoogle Scholar
11. Early, T. O., Drewes, D. R., and Jacobs, G. K., in Geochemical Behavior of Disposed Radioactive Waste, ACS Symp. Series 246, pp 147–166, 1984.CrossRefGoogle Scholar