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Long Term Field Leaching Studies of Simulated Nuclear Waste Glass in Granite and Salt

Published online by Cambridge University Press:  25 February 2011

R.L. Schulz ,
D.E. Clark ,
A.R. Lodding  and
G.G. Wicks
R.L. Schulz
Affiliation:
University of Florida, Dept. of Materials Science and Engineering, Gainesville, Florida, USA
D.E. Clark
Affiliation:
University of Florida, Dept. of Materials Science and Engineering, Gainesville, Florida, USA
A.R. Lodding
Affiliation:
Chalmers University of Technology, Physics Dept., Gothenburg, SWEDEN
G.G. Wicks
Affiliation:
Westinghouse Savannah River Co., Aiken, South Carolina, USA
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Abstract

Field leaching studies were carried out in granite at the Stripa site in Sweden and also in salt in the Materials Interface Interaction Test at the Waste Isolation Pilot Plant (MIIT/WIPP) in New Mexico. The goal of these studies is to assess the durability of various glass compositions engineered to isolate high-level nuclear waste from the biosphere. An additional goal of the MIIT study is to determine how the glasses interact with a wide array of proposed materials that may be a part of the multi-barrier waste package. These substances include metals, geological host specimens,, as well as engineered backfill and overpack materials.

Two year data on the SRLY (165/TDS) glass compositions has been extracted from both studies (Stripa and WIPP/MIIT) and five year data has recently become available from the MIIT study. Results from SEM/EDS, SIMS and FTIRRS analyses on glass/glass interfaces are presented in this paper.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 257: Symposium – Scientific Basis for Nuclear Waste Management XV , 1991 , 65
Copyright
Copyright © Materials Research Society 1992

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References

REFERENCES

1. Wicks, G.G. and Bickford, D. Tech. Rev., 51-58, Nov-Dec. 1989.Google Scholar
2. Clark, D.E., Zhu, B.F. and Robinson, R.S., in, Advances in Ceramics, Vol. 8, Nuclear Waste Management, edited by Wicks, G.G., and Ross, W.A.. (American Ceramic Society, Ohio, 1984) 324–336.Google Scholar
3. Wicks, G.G. and Molecke, M. in, Advances in Ceramics, Vol. 20, Nuclear Waste Management II, edited by Clark, D.E., White, W.B. and Machiels, A.J., (American Ceramic Society, Ohio, 1986) 657–667.Google Scholar
4. Lodding, A.R., Engstrom, E.U., Clark, D.E., Werme, L.O. and Wicks, G.G., in Advances in Ceramics, Vol. 20, Nuclear Waste Management II, edited by Clark, D.E., White, W.B. and Machiels, A.J., (American Ceramic Society, Ohio, 1986) 567–581.Google Scholar
5. Zhu, B.F., Clark, D.E., Lodding, A.R., Wicks, G.G., in Advances in Ceramics, Vol. 20, Nuclear Waste Management II, edited by Clark, D.E., White, W.B. and Machiels, A.J., (American Ceramic Society, Ohio, 1986) 591–599.Google Scholar