Diffusion of Cesium in Sodium Borosilicate Glasses for Nuclear Waste Immobilisation

MRS Online Proceedings Library volume 176, Article number: 441 (1989) Cite this article

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.

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Author information

Affiliations

  1. Chemical Research Department, N.V. KEMA, R&D division, P.O. Box 9035, Arnhem, ET, 6800, The Netherlands

    E. G. F. Sengersi & F. J. J. G. Janssen

  2. TNO Institute of Applied Physics - Glass Technology Department, P.O. Box 513, Eindhoven, MB, 5600, The Netherlands

    H. de Waal

Authors
  1. E. G. F. Sengersi
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  2. F. J. J. G. Janssen
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  3. H. de Waal
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Sengersi, E.G.F., Janssen, F.J.J.G. & de Waal, H. Diffusion of Cesium in Sodium Borosilicate Glasses for Nuclear Waste Immobilisation. MRS Online Proceedings Library 176, 441 (1989). https://doi.org/10.1557/PROC-176-441

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