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

  • R.L. Schulz (a1), D.E. Clark (a1), A.R. Lodding (a2) and G.G. Wicks (a3)

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.

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References

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1. Wicks, G.G. and Bickford, D. Tech. Rev., 51-58, Nov-Dec. 1989.
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) 324336.
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) 657667.
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) 567581.
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) 591599.

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