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Influence of Alloy Microstructure on Oxide Growth in HCM12A in Supercritical Water

Published online by Cambridge University Press:  15 March 2011

Jeremy Bischoff ,
Arthur T. Motta ,
Lizhen Tan  and
Todd R. Allen
Jeremy Bischoff
Affiliation:
Department of Mechanical and Nuclear Engineering, Pennsylvania State University, 227 Reber Building, University Park, PA, 16802, USA.
Arthur T. Motta
Affiliation:
Department of Mechanical and Nuclear Engineering, Pennsylvania State University, 227 Reber Building, University Park, PA, 16802, USA.
Lizhen Tan
Affiliation:
Department of Engineering Physics, University of Wisconsin-Madison, 1500 Engineering Drive, Madison, WI 53706, USA.
Todd R. Allen
Affiliation:
Department of Engineering Physics, University of Wisconsin-Madison, 1500 Engineering Drive, Madison, WI 53706, USA.
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Abstract

HCM12A is a ferritic-martensitic steel alloy envisioned for cladding and structural material in the Generation IV Supercritical Water Reactor (SCWR). This alloy was oxidized in 600°C supercritical water for 2, 4 and 6 weeks, and the oxide layers formed were analyzed using microbeam synchrotron radiation and electron microscopy. The oxide layers show a three-layer structure with an Fe3O4 outer layer, an inner layer containing a mixture of Fe3O4 and FeCr2O4 and a diffusion layer containing FeCr2O4 and Cr2O3 precipitates along ferrite lath boundaries. The base metal microstructure has a strong influence on the advancement of the oxide layers, due to the segregation at the lath boundaries of chromium rich particles, which are oxidized preferentially.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 1125: Symposium R – Materials for Future Fusion and Fission Technologies , 2008 , 1125-R06-05
Copyright
Copyright © Materials Research Society 2009

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References

REFERENCES

[1] “A Technology Roadmap for Generation IV Nuclear Energy Systems,” U.S. DOE NERAC and Generation IV International Forum GIF-002-00, 2002.Google Scholar
[2] Tan, L., Machut, M. T., Sridharan, K., and Allen, T. R., J. of Nucl. Materials, 371, (2007), 161–170.Google Scholar
[3] Tan, L., Yang, Y., and Allen, T. R., Corrosion Science, 48, (2006), 4234–4242.Google Scholar
[4] Tan, L., Yang, Y., and Allen, T. R., Corrosion Science, 48, (2006), 3123–3138.Google Scholar
[5] Sridharan, K., Harrington, S. P., Johnson, A. K., Licht, J. R., Anderson, M. H., and Allen, T. R., Materials & Design, 28, (2007), 1177–1185.Google Scholar
[6] Sridharan, K., Zillmer, A., Licht, J. R., Allen, T. R., Anderson, M. H., and Tan, L., “Corrosion Behavior of Candidate Alloys for Supercritical Water Reactors,” Proceedings of ICAPP 04, Pittsburgh, PA, (2004).Google Scholar
[7] Yilmazbayhan, A., Motta, A. T., Comstock, R. J., Sabol, G. P., Lai, B., and Cai, Z., Journal of Nuclear Materials, 324, (2004), 6–22.Google Scholar
[8] Motta, A. T., Siwy, A. D., Kunkle, J. M., Bischoff, J. B., Comstock, R. J., Chen, Y., and Allen, T. R., “Microbeam Synchrotron Radiation Diffraction and Fluorescence Study of Oxide Layers formed on 9CrODS Steel in Supercritical Water,” Proceedings of 13th Environmental Degradation of Materials in Nuclear Power Plants, (2007).Google Scholar
[9] Bischoff, J., Motta, A. T., and Comstock, R. J., J. of Nucl. Materials, in press, accepted manuscript (2009).Google Scholar
[10] Siwy, A. D., Clark, T. E., and Motta, A. T., J. of Nucl. Materials, in press, accepted manuscript (2009).Google Scholar