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This is the final report on work conducted to investigate the long-term behaviour of fission product containment glass from the standpoint of their aqueous alteration. This is an important aspect in demonstrating the safety of geological disposal of vitrified waste packages.

The objectives were:
to model the alteration kinetics of the glass package in order to assess the performance of the primary barrier under realistic disposal conditions;
to model the release of the major radionuclides contained in the glass in order to obtain a glass source term for incorporation in the general codes that take into account migration and transport to the biosphere for safety purposes. es.

Additional information

Authors: ADVOCAT T, CEA Valrhô, Bagnols-sur-Cèze (FR);GIN S, CEA Valrhô, Bagnols-sur-Cèze (FR);GODON N, CEA Valrhô, Bagnols-sur-Cèze (FR);JOLLIVET P, CEA Valrhô, Bagnols-sur-Cèze (FR);VERNAZ E, CEA Valrhô, Bagnols-sur-Cèze (FR)
Bibliographic Reference: EUR 17113 EN (1997) 100pp., FS, ECU 18.50
Availability: Available from the (2)
ISBN: ISBN 92-827-8732-X
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