ETUDES DE CORROSION DES MATERIAUX DE CONTENEURS POUR LE STOCKAGE DES DECHETS RADIOACTIFS EN SITES GRANITIQUES.
This report describes the research carried out for the assessment of corrosion behaviour of materials selected for the manufacture of containers for disposal of radioactive waste in granite formation. Metals and alloys included in laboratory test program were: - Titanium and Titanium + 0.2 % Palladium; - Zircaloy 4; - Hastelloy C-276; - 625 and 825 Alloys; - 600 and 800 Alloys; - 316 L and 304 L Stainless Steels. Test solutions were designed on the basis of a synthetic groundwater, the concentration of some ions (e.g. Cl- and OH-) being increased. Temperature was 80 degrees C. General corrosion rate was evaluated on non-pitted metals and was very low after a 4 month immersion test. Maximal rates (expressed as thickness of oxidized or dissolved metallic layer per unit of time) are: - Zircaloy 4 0.03mum/y - Hastelloy C-276, Titanium and Titanium - Palladium..0.15mum/y - 625 Alloy .......................................0.40mum/y Pitting corrosion is observed on stainless steels and on 600, 800 and 825 Alloys. Zircaloy could be susceptible to this type of attack in particular conditions (coupling with more noble metals). Titanium, Titanium - Palladium, Hastelloy C-276 and 625 Alloy are not affected by pitting in the test conditions. Other aspects under investigation were crevise corrosion, stress corrosion cracking, and thermal treatment.
Références bibliographiques: EUR 8762 FR (1984) FS, 91 P., BFR 300, EUROFFICE, LUXEMBOURG, POB 1003
Disponibilité: Can be ordered online
Numéro d'enregistrement: 1989122060300 / Dernière mise à jour le: 1987-01-01
Langues disponibles: fr