Oxidation behavior of ferritic-martensitic and ODS steels in supercritical water

Jeremy Bischoff, Arthur T. Motta

Research output: Contribution to journalArticlepeer-review

149 Scopus citations


Ferritic-martensitic and ODS alloys are primary candidates for application as cladding and structural materials in the Generation IV Supercritical Water Reactor. One of the main in-service degradation mechanisms for these alloys is uniform corrosion. This article analyzes the oxide microstructure formed on these alloys to better understand their oxidation behavior. Corrosion tests were performed in both steam and supercritical water (SCW) at 500 and 600°C. The oxide microstructure was analyzed using microbeam synchrotron radiation diffraction and fluorescence associated with electron microscopy. The oxide forms a three-layer structure with an outer layer containing only Fe 3O4, an inner layer containing a non-uniform (Fe,Cr) 3O4 spinel structure, and a diffusion layer containing a mixture of metal grains and chromium-rich precipitates. A marker experiment located the original water-metal interface as the outer-inner layer interface implying a mechanism where iron migrates outwards to form the outer layer and oxygen diffuses inwards to form the inner layer.

Original languageEnglish (US)
Pages (from-to)261-276
Number of pages16
JournalJournal of Nuclear Materials
Issue number1-3
StatePublished - May 2012

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • General Materials Science
  • Nuclear Energy and Engineering


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