On the role of oxygen partial pressure on the composition of the oxide layer formed on alloy 690 at 700°C

Magali Moeglen (1, 2) , Stéphane Perrin (2) , Loic Marchetti (3) , Michel Tabarant (4) , Marc Foucault (5) , Yves Wouters (1)

1 SIMaP - Science et Ingénierie des Matériaux et Procédés
2 SCCME - Service de la Corrosion et du Comportement des Matériaux dans leur Environnement
3 LECA - Laboratoire d'Etude de la Corrosion Aqueuse
4 LANIE - Laboratoire de développement Analytique Nucléaire Isotopique et Elémentaire
5 Areva NP

Steam generator tubes in pressurized water reactors (PWR) are made of nickel based alloy such as alloy 600 or alloy 690. During oxidation process of this alloy in water at high temperature, nickel cations are released in the primary media. After neutron flux exposure in the reactor core, these cations can turn into radioactive products, such as 58Co. If carried through the primary circuit, these radioactive products precipitate and contaminate the loop, making maintenance more difficult.

Mots clés: Alloy 690; oxidation; oxygen partial pressure; O$_2$ dissociation catalysis

Domaines: Physique Nucléaire Théorique [nucl-th]; Physique Nucléaire Expérimentale [nucl-ex]

Magali Moeglen, Stéphane Perrin, Loic Marchetti, Michel Tabarant, Marc Foucault, et al.. On the role of oxygen partial pressure on the composition of the oxide layer formed on alloy 690 at 700°C. HTCPM 2016 - 9th International Symposium on High-Temperature Corrosion and Protection of Materials, May 2016, Les Embiez, France. ⟨cea-02499858⟩