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Ceramic Containers for Spent Nuclear Fuel. I. Homogeneous Sealing of Rutile Containers at Low Temperatures

Published online by Cambridge University Press:  26 February 2011

S Forberg  and
B Bergman
S Forberg
Affiliation:
Dept. of Nuclear ChemistryThe Royal Institute of Technology, S-100 44 Stockholm, Sweden
B Bergman
Affiliation:
Dept. of Physical Metallurgy and CeramicsThe Royal Institute of Technology, S-100 44 Stockholm, Sweden
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Abstract

Some ceramic materials may withstand granitic ground water for millions of years, or, ideally be thermodynamically stable under these conditions. Some conceptual design criteria and materials selection guidelines are discussed with reference to ceramic containers for spent fuel.

Rutile was chosen for practical studies. One reason for this choice was the possibility of joining lid and container below 950°C. TiO2 with 0.1–1.0 w/o B, added as B or B2O3, was densified at 900°C by hot pressing; 0.25 w/o B was used for bonding.

TiO2 from a sol-gel process was, without additions, used for bonding at 900°C and at 800°C. A new TiO2 raw material was, without sintering aids, pressed to high density at 930°C, and also used for joining experiments.

Some bonds are shown in micrographs. The major result is that nearly homogeneous bonding at 900°C seems feasible. The new raw material might possibly be processed to a monolithic ceramic body outside the fuel without any need for sealing.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 44: Symposium N – Scientific Basis for Nuclear Waste Management VIII , 1984 , 421
Copyright
Copyright © Materials Research Society 1985

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References

[1] International Nuclear Fuel Cycle Evaluation(IAEA, Vienna 1980).Google Scholar
[2] Final Storage of Spent Nuclear Fuel - KBS-3, Swedish Nuclear Fuel and Waste Management Co (SKB, Stockholm, May 1983).Google Scholar
[3] Nuttall, K., Crosthwaite, J.L., McKay, P., Mathew, P.M., Teper, B., Maak, P.Y.Y. and Moles, M.D.C., in Scientific Basis for Nuclear Waste Management Vl, edited by Brookins, D.G.,”(North-Holland, N.Y. 1983), p. 677.Google Scholar
[4] “Andere Entsorgungstechniken,Halbjahresbericht AE Nr 15 (in German), Kernforschungszentrum Karlsruhe, FRG, Marz 1984.Google Scholar
[5] Fullam, H.T. and Skiens, W.E., in Scientific Basis for Nuclear Waste Management III, edited by Moore, J.G., (Plenum Press, N.Y., 1981), p.531.Google Scholar
[6] Burnett, N.C. and Hootan, R.D., in Nuclear Waste Management, edited by Wicks, G.G. and Ross, W.A. (The American Ceramic Society, Inc., Columbus, Ohio, USA 1984), p. 456.Google Scholar
[7] “Andere Entsorgungstechniken”, Abschlussbericht der Projektphase I, AE Nr 9 (in German) (Kernforschungszentrum Karlsruhe, FRG, August 1982).Google Scholar
[8]. Onofrei, M., AECL, Whiteshell, Pinawa, Manitoba, Canada. Personal communication, Nov. 18, 1983.Google Scholar
[9] Larker, H., Lundgren, J. and Tegman, R., “Direct Deposition of Spent Nuclear Fuel in Corundum Containers”; (in Swedish), a Report from ASEA, Robertsfors, Sweden to SKB, Stockholm, 1979.Google Scholar
[10] Ohman, L.-O., Ingri, N. and Tegman, R., Ceramic Bulletin 61, 567 (1982).Google Scholar
[11] Bergman, B. and Forberg, S., II “Reactions Between TiO2 and the Steel Canning during Hot Isostatic Processing”, this symposium.Google Scholar
[12] Nesbitt, H.W., Bancroft, G.M., Karkhanis, S.N. and Fyfe, W.S., in Scientific Basis for Nuclear Waste Management III, edited by Moore, J.G. (Plenum Press, N.Y. 1981), p. 131.CrossRefGoogle Scholar
[13] Hayward, P.J., Hocking, W.H., Doern, F.E. and Cecchetto, E.V., in Scientific Basis for Nuclear Waste Management V, edited by Lutze, W., (North-Holland, N.Y. 1982), p. 319.Google Scholar
[14] Metson, J.B., Bancroft, G.M., Kanetkar, S.M., Nesbitt, H.W., Fyfe, W.S. and Hayward, P.J., in Scientific Basis for Nuclear Waste Management V, edited by Lutze, W., (North-Holland, N.Y. 1982) p. 329.Google Scholar
[15] Dosch, R.G., Lynch, A.W., Headley, T.T. and Hlava, P.F., in Scientific Basis for Nuclear Waste Management III, edited by Moore, J.G., (Plenum Press, N.Y. 1981), p. 123.Google Scholar
[16] Bauer, C., ”Ein mogliches Endlagerprodukt fur Hochradioaktiven Abfall aus Wiederaufarbeitungsanlagen auf der Grundlage eines Uberblicks uber die Verfestigung und Endlagerung von Hochradioaktivem Abfall”, Diss. (Universitat Karlsruhe, FRG 1982).Google Scholar
[17] Urwin, U., Tioxide UK Limited, Stockton-on-Tees, Cleveland TS18 2NO England, personal communication June 6, 1984.Google Scholar
[18] Komarneni, S., Materials Research Laboratory, The Pennsylvania State University, University Park., PA, USA, personal communication May 8, 1984.Google Scholar
[19] Birchall, J.D. and Kelly, A., Scientific American, p.88, May 1983).Google Scholar
[20] Barnes, M.W. and Roy, D.M., in Scientific Basis for Nuclear Waste Management VII, edited by McVay, G.L., (North-Holland, N.Y. 1984).Google Scholar
[21] Roy, R., Materials Research Laboratory, The Pennsylvania State University, University Park, PA, USA, personal communication May 1984.Google Scholar