TY - JOUR
T1 - Oxidation behavior of ferritic-martensitic and ODS steels in supercritical water
AU - Bischoff, Jeremy
AU - Motta, Arthur T.
N1 - Funding Information:
The authors would like to thank Zhonghou Cai for his help acquiring data at the APS in Argonne National Laboratory, and Trevor Clark and Joe Kulik for their help in the TEM sample preparation and examination. The authors would also like to thank Yann de Carlan at the CEA for the use of the 14CrODS alloy produced at the CEA. This publication was supported by the Pennsylvania State University Materials Research Institute Nanofabrication Lab and the National Science Foundation Cooperative Agreement No. 0335765, National Nanotechnology Infrastructure Network, with Cornell University. This study was funded by DOE-NERI Project DE-FC07-06ID14744. The use of the APS was supported by the DOE, Basic Energy Sciences, Office of Science under Contract No. W-31-109-Eng-38.
PY - 2012/5
Y1 - 2012/5
N2 - 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.
AB - 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.
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U2 - 10.1016/j.jnucmat.2012.03.009
DO - 10.1016/j.jnucmat.2012.03.009
M3 - Article
AN - SCOPUS:84859633659
SN - 0022-3115
VL - 424
SP - 261
EP - 276
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
IS - 1-3
ER -