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Diffusion of Cesium in Sodium Borosilicate Glasses for Nuclear Waste Immobilisation

Published online by Cambridge University Press:  21 February 2011

E.G.F. Sengersi ,
F.J.J.G. Janssen  and
H. de Waal
E.G.F. Sengersi
Affiliation:
N.V. KEMA, R&D division, Chemical Research Department, P.O. Box 9035, 6800 ET Arnhem, The Netherlands
F.J.J.G. Janssen
Affiliation:
N.V. KEMA, R&D division, Chemical Research Department, P.O. Box 9035, 6800 ET Arnhem, The Netherlands
H. de Waal
Affiliation:
TNO Institute of Applied Physics - Glass Technology Department, P.O. Box 513, 5600 MB Eindhoven, The Netherlands
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Abstract

Diffusion of cesium in borosilicate glass for high-level radioactive waste is discussed. For this purpose model glasses with non-radioactive elements are being made, in accordance with the specifications of the reprocessing plants, from which concentration couples are composed. A concentration couple consists of two cylinders of borosilicate glass which contain different amounts of cesium. After heat treatment the couples are studied by means of scanning electron microscopy and X-Ray microanalysis. The model study will provide a basis for predictions of the containment achieved over a longer period of time.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 176: Symposium U – Scientific Basis for Nuclear Waste Management XIII , 1989 , 441
Copyright
Copyright © Materials Research Society 1990

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References

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