Influence of oxide films on primary water stress corrosion cracking initiation of alloy 600

J. Panter (1) , Bernard Viguier (1) , J.M Cloué , M. Foucault , P. Combrade , Eric Andrieu (1)

1 CIRIMAT - Centre interuniversitaire de recherche et d'ingenierie des matériaux

In the present study alloy 600 was tested in simulated pressurised water reactor (PWR) primary water, at 360 °C, under an hydrogen partial pressure of 30 kPa. These testing conditions correspond to the maximum sensitivity of alloy 600 to crack initiation. The resulting oxidised structures (corrosion scale and underlying metal) were characterised. A chromium rich oxide layer was revealed, the underlying metal being chromium depleted. In addition, analysis of the chemical composition of the metal close to the oxide scale had allowed to detect oxygen under the oxide scale and particularly in a triple grain boundary. Implication of such a finding on the crack initiation of alloy 600 is discussed. Significant diminution of the crack initiation time was observed for sample oxidised before stress corrosion tests. In view of these results, a mechanism for stress corrosion crack initiation of alloy 600 in PWR primary water was proposed.

Mots clés: Oxide films; Alloy 600; PWR; Pressurised water reactor; Stress; Corrosion; Cracking initiation

Domaines: Matériaux

J. Panter, Bernard Viguier, J.M Cloué, M. Foucault, P. Combrade, et al.. Influence of oxide films on primary water stress corrosion cracking initiation of alloy 600. Journal of Nuclear Materials, 2006, vol. 348, Available on : http://oatao.univ-toulouse.fr/651/1/Viguier_651.pdf ,. ⟨10.1016/j.jnucmat.2005.10.002⟩. ⟨hal-00477641⟩