Comparison of the corrosion behavior of the 14Cr ODS alloy in steam and supercritical water

Jeremy Bischoff, Arthur Thompson Motta

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

The 14CrODS alloy was corroded in both steam and supercritical water (SCW) at 500°C The weight gain observed in SCW was consistently about 1.5 times higher than that in steam and the corrosion rate was higher in SCW compared to steam. To explain this discrepancy, the oxide microstructure of samples corroded in both environments was analyzed using microbeam synchrotron diffraction and fluorescence, and scanning electron microscopy (SEM). In both environments, the oxide formed a three-layer structure, similar to previous observations on ferritic-martensitic alloys. Compared to the SCW samples, the steam samples exhibited thinner and denser oxide layers, which contained more Cr 2O 3 especially at specific interfaces. These results are discussed and an explanation for the divergence in oxidation behavior between steam and SCW is proposed.

Original languageEnglish (US)
Title of host publication15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
Pages1837-1845
Number of pages9
StatePublished - Dec 1 2011
Event15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011 - Colorado Springs, CO, United States
Duration: Aug 7 2011Aug 11 2011

Publication series

Name15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
Volume3

Other

Other15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
CountryUnited States
CityColorado Springs, CO
Period8/7/118/11/11

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Pollution

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