TY - GEN
T1 - Comparison of the corrosion behavior of the 14Cr ODS alloy in steam and supercritical water
AU - Bischoff, Jeremy
AU - Motta, Arthur Thompson
PY - 2011
Y1 - 2011
N2 - 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.
AB - 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.
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M3 - Conference contribution
AN - SCOPUS:84867598318
SN - 9781622761944
T3 - 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
SP - 1837
EP - 1845
BT - 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
T2 - 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
Y2 - 7 August 2011 through 11 August 2011
ER -