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Transmission Electron Microscopy of Corrosion of Stainless Steel-Zirconium Metal Waste Forms

Published online by Cambridge University Press:  02 July 2020

J.S. Luo
Affiliation:
Argonne National Laboratory, Argonne, IL60439
D.P. Abraham
Affiliation:
Argonne National Laboratory, Argonne, IL60439
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Extract

Stainless steel-zirconium (SS-Zr) alloys have been developed as waste forms to immobilize and retain fission products generated during the electrometallurgical treatment of spent nuclear fuel. The baseline waste form is a stainless steel-15 wt.% zirconium (SS-15Zr) alloy, which is prepared by melting appropriate amount of Type 316 stainless steel (SS316) and high purity zirconium. As zirconium has very low solubility in iron, the addition of zirconium to SS316 results in the formation of ZrFe2 -type Laves intermetallic phases. The corrosion behavior of stainless steel has been widely studied; however, the corrosion behavior of the Zr-based-intermetallic has not been previously investigated. In this paper, we present a microstructural characterization of the corrosion layer formed on the Zr-intermetallic phase using energy-filtering transmission electron microscopy (TEM) and energy dispersive x-ray spectroscopy (EDS).

Specimens of SS-15Zr alloy, crushed to 75 to 150 μm sizes, were immersed in 90°C deionized water for a period of two years.

Type
Oxidation/Corrosion
Copyright
Copyright © Microscopy Society of America

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References

1. McDeavitt, S.M., Abraham, D.P., and Park, J.Y., J. Nucl. Mater. 257(1998)2134.CrossRefGoogle Scholar

2. Jones, D.A., Principles and Prevention of Corrosion, Macmillan Publishing (1992).Google Scholar

3. This research was sponsored by the U. S. Department of Energy, as part of a DOE program to develop electric power technology, under Contract W-31-109-ENG-38.Google Scholar