Hostname: page-component-8448b6f56d-gtxcr Total loading time: 0 Render date: 2024-04-23T21:33:03.569Z Has data issue: false hasContentIssue false
  • English
  • Français

Nuclear Waste Glass Interfaces after 1 year Burial in Stripa

Published online by Cambridge University Press:  26 February 2011

L O Werme ,
L L Hench  and
A Lodding
L O Werme
Affiliation:
Swedish Nuclear Fuel and Waste Management Co, Stockholm, Sweden
L L Hench
Affiliation:
Department of Materials Science and Engineering, University of Florida, Gainesville, Florida
A Lodding
Affiliation:
Chalmers University of Technology, Gothenburg, Sweden
Get access

Abstract

Interface reactions between two nuclear waste borosilicate glasses and repository components have been studied in an in-situ burial experiment in Stripa mine, Sweden. Exposures up to one year have been analyzed and are reported.

The results obtained up to date show an increased depth of attack ranging by: increased severity from the glass/granite interfaces, glass/glass interfaces to glass/bentonite interfaces. The rate and extent of surface attack is discussed in terms of ion exchange with species from the groundwater and leached from the repository components.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 44: Symposium N – Scientific Basis for Nuclear Waste Management VIII , 1984 , 37
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] Hench, L.L, Werme, L., and Lodding, A., Sci. Basis for Nucl. Waste Mgt.-V, ed. Lutze, W., Elsevier Sci. Publ. Co, NY (1982), 153.Google Scholar
[2] Werme, L.,.Hench, L.L., and Lodding, A., Sci. Basis for Nucl. Waste Mgt.- V, ed. Lutze, W., Elsevier Sci. Publ. Co, NY (1982) 135.Google Scholar
[3] Hench, L.L., Lodding, A., and Werme, L., Adv.in Ceram., 8, 310, eds. Wicks, G.G. and Ross, W.A., Am. Ceram. Soc., Columbus, OH (1984).Google Scholar
[4] Lodding, A. and Odelius, H., Microchim. Acta, Suppl. 10 (1983) 21.CrossRefGoogle Scholar
[5] Christensen, H., Hermansson, H.-P., Hillver, M., and Olilla, K.K., Studsvik Energiteknik AB, Report Studsvik /NW-82/247, Studsvik, Sweden,(1982).Google Scholar
[6] Christensen, H., Hermansson, H.-P., and Bjorner, I.-K., Studsvik Energiteknik AB, Report Studsvik/NW-84/638, Studsvik, Sweden,(1984).Google Scholar
[7] Nogues, J.-L., Hench, L.L. and Zarzycki, J., Sci. Basis for Nucl. Waste Mgt.-V, Ed. Lutze, W., Elsevier Sci. Publ.Co, NY (1982) 211.Google Scholar
[8] Hench, L.L., J. Physique, Colloque C9,49 (1982) 625.Google Scholar
[9] Wallace, R.M. and Wicks, G.G., Sci. Basis for Nucl. Waste Mgt.-VI, Ed. Brookins, D.G., Elsevier Sci. Publ.Co, NY (1983) 167.Google Scholar
[10] Grambow, B., Sci. Basis for Nucl. Waste Mgt.-V, ed. Lutze, W., Elsevier Sci. Publ. Co., NY (1982) 93.Google Scholar
[11] Dilmore, M.F., Clark, O.E. and Hench, L.L., Bull. Am. Ceram. 61 (1978) 439.Google Scholar
[12] Clark, O.E., Pantano, C.G. and Hench, L.L., Glass Corrosion, Bks for Ind., NY (1979).Google Scholar
[13] Paul, A., Chem. of Glasses, Chapman and Hall, London (1982).Google Scholar
[14] Clark, O.E., Swedish Nucl. Fuel and Waste Mgt. Co. KBS, Tech. Report, to be published.Google Scholar
[15] Plodinec, M.J., Jantzen, C.M. and Wicks, G.G., Adv. in Ceram., 8, 491, eds. Wicks, G.G. and Ross, W.A., Am. Ceram. Soc., Columbus, OH (1984).Google Scholar
[16] Christensen, H., Hermansson, H.-P., Clark, O.E. and Werme, L., Adv. In Ceram., 8, 346, eds. Wicks, G.G. and Ross, W.A., Am. Ceram. Soc., Columbus OH (1984).Google Scholar
[17] Iseghem, P. van, Timmermans, W. and DeBatist, R., Sci. Basis for Nucl. Waste Mgt.-V, ed.Lutze, W., Elsevier Sci. Publ. Co., NY (1982), 219.Google Scholar