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Abstract

For performance assessment of high-level radioactive waste disposal in salt formations, corrosion tests were performed at FZK, using high active R7T7-type glass contacting saline solutions. The objective of this investigation was to describe the extent to which Np, Pu, Am and Tc are mobilized from vitrified high-level waste into the near field, when a repository-relevant (Gorleben salt dome) concentrated salt solution intrudes the emplacement locations. As far as reaction kinetics are concerned the results clearly show that active and inactive glasses behave similarly. Hence, the large database generated for inactive glass can also be used quantitatively to explain results of the active experiment. Consequently, as far as the evolution of the solution composition and of the pH with time is concerned, long-term predictions of the behaviour of the release properties of actinides and Tc from the active glass can be based to a large extent on the results obtained from inactive tests. The rate law described can only be used for the formulation of a source term for glass performance in a repository, if its validity in the presence of other engineered and natural barrier materials has been tested.

Additional information

Authors: GRAMBOW B ET AL, Forschungszentrum Karlsruhe GmbH (DE);LUTZE W, University of New Mexico, Albuquerque (US)
Bibliographic Reference: EUR 17114 EN (1997) 105pp., FS, ECU 20
Availability: Available from the (2)
ISBN: ISBN 92-827-5316-6
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