CORROSION BEHAVIOUR OF CONTAINER MATERIALS FOR GEOLOGICAL DISPOSAL OF HIGH LEVEL WASTE
Within the framework of the Community R&D programme on management and storage of radioactive waste (shared cost action), a research activity is aiming at the assessment of corrosion behaviour of potential container materials for geological disposal of vitrified high level wastes. In this report, the results obtained during the year 1983 are described. Research performed at the Studiecentrum voor Kernenergie - Centre d'Etudes de l'Energie nucleaire (SCK/CEN) at Mol (B), concerns the corrosion behaviour in clay environments. The behaviour in salt is tested by the Kernforschungszentrum (KfK) at Karlsruhe (D). Corrosion behaviour in granitic environments is being examined by the Commissariat a l'Energie Atomique (CEA) at Fontenay-aux-Roses (F) and the Atomic Energy Research Establishment (AERE) at Harwell (UK); the first is concentrating on corrosion resistant materials and the latter on corrosion allowance materials. Finally, the Centre national de la recherche scientifique (CNRS) at Vitry (F) is examining the formation and behaviour of passive layers on the metal alloys in the various environments.
Bibliographic Reference: EUR 9570 EN (1985) FS, 193 P., BFR 600, EUROFFICE,
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Record Number: 1989123058600 / Last updated on: 1987-01-01
Available languages: en