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

Abstract : 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.
Document type :
Journal articles
Complete list of metadatas

https://hal.archives-ouvertes.fr/hal-00477641
Contributor : Open Archive Toulouse Archive Ouverte (oatao) <>
Submitted on : Thursday, April 29, 2010 - 5:20:55 PM
Last modification on : Friday, June 14, 2019 - 6:31:04 PM

Links full text

Identifiers

Collections

Citation

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, Elsevier, 2006, vol. 348, Available on : http://oatao.univ-toulouse.fr/651/1/Viguier_651.pdf ,. ⟨10.1016/j.jnucmat.2005.10.002⟩. ⟨hal-00477641⟩

Share

Metrics

Record views

67