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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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