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For the assessment of the potential performance of directly disposed spent fuel in a nuclear waste repository in salt formations the chemical reactions of the fuel with possibly intruding saline brines must be understood and the associated radionuclide release must be quantified. In this context a large research project has been conducted, combining experimental approaches (in particular leach or corrosion tests) with modelling techniques. For comparison, experiments were also performed with as fabricated UO(2). Static dissolution experiments of prewashed spent fuel samples were performed in anaerobic NaCl solutions and deionized water at room temperature, clearly demonstrating the suitability of low temperature tests for assessing spent fuel behaviour over large ranges of temperature, as expected in a final repository. The dependency of reaction rates on surface area to solution volume was rationalized by radiolysis effects.

Additional information

Authors: GRAMBOW B ET AL, Forschungszentrum Karlsruhe GmbH (DE);GAGO J, Empresa Nacional de Residuos Radiactivos SA, (ES);CASAS I ET AL, Universidad Politécnica de Cataluña (ES)
Bibliographic Reference: EUR 17111 EN (1997) 166pp., FS, ECU 30
Availability: Available from the (2)
ISBN: ISBN 92-827-9572-1
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