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Alterability of the French LWR Solution Reference Glass in Repository Conditions

Published online by Cambridge University Press:  26 February 2011

J. L. Nogues ,
E. Y. Vernaz ,
N. Jacquet-Francillon  and
S. Pasquini
J. L. Nogues
Affiliation:
CEA/CEN Valrho, BP 171, 30205 - Bagnols-sur-Cèze, FRANCE
E. Y. Vernaz
Affiliation:
CEA/CEN Valrho, BP 171, 30205 - Bagnols-sur-Cèze, FRANCE
N. Jacquet-Francillon
Affiliation:
CEA/CEN Valrho, BP 171, 30205 - Bagnols-sur-Cèze, FRANCE
S. Pasquini
Affiliation:
CEA/CEN Cadarache, BP 1, 13115 - Saint-Paul-lez-Durance, FRANCE
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Abstract

The disposal of glass blocks containing fission products in granitic geological formations is one of the options currently investigated in France. This paper discusses the major criteria selected to develop models of such repositories and gives the first results obtained with the corresponding experimental test. Five laboratory mockups corresponding to different alternatives regarding the fill materials were prepared. The following materials were used to encase the French LWR reference glass:

- Test I : Granite, sand, stainless steel;

- Test 2 : Granite, sand, illite, stainless steel;

- Test 3 : Granite, sand, bentonite, stainless steel;

- Test 4 : Granite, sand, Al2O3, ceramic, stainless steel;

- Test 5 : Granite, sand, haitalloy C4.

Samples were taken of the solutions obtained in the preconditioning cell and in contact with the glass to assess the glass corrosion behavior in each of these media. The experiments were completed by surface analyses designed to compare the morphology of the surface layers that develop with and without the environmental materials.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 44: Symposium N – Scientific Basis for Nuclear Waste Management VIII , 1984 , 195
Copyright
Copyright © Materials Research Society 1985

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References

1. Nogues, J.L., Vernaz, E.Y., Jacquet-Francillon-Nuclear, N. glass corrosion mechanisms applied to the French LWR reference glass - Materials Research Society 1984 Fall Meeting, Scientific Basis for Nuclear Waste Management Proceedings.CrossRefGoogle Scholar
2. Nogues, J.L. - Les mécanismes de corrosion des verres de confinement des produits de fission. Thèse - Université des Sciences et Techniques du Languedoc - Montpellier 1984 (in French).Google Scholar
3. Nogues, J.L., Terki, A. - Influence du mode de lixiviation sur l'altérabilité d'un verre de confinement des produits de fission. Union Scientifique Continentale du Verre 1984.Google Scholar
4. Nogues, J.L., Vernaz, E., Jacquet-Francillon, N., Pasquini, S. - Interaction between a nuclear glass and nearfield materials in various rigs simulating a geological disposal - Submitted to International Seminar on suitability of radioactive waste products for disposal. Kernforschungsanlage, Julich, FRG, 10–14 June 1985 Google Scholar