Characterization of oxidation products on a ZrFe{sub 2}-type laves intermetallic exposed to 200{degree}C steam.

Conference · Mon Nov 20 04:00:00 EST 2000

OSTI ID:768627

Abraham, D P; Dietz, N; Finnegan, N

The release of radioactive elements from the stainless steel-15 wt% zirconium (SS-15Zr) metal waste form will be governed by the corrosion behavior of ZrFe{sub 2}-type intermetallics phases present in the alloy. In this article, oxidation products that formed on a ZrFe{sub 2}-type intermetallic sample exposed to 200 C steam were characterized by Auger Electron Spectroscopy (AES) and Transmission Electron Microscopy (TEM). The data revealed two oxide layers on the sample surface: an outer crystalline iron-oxide layer and an inner amorphous zirconium-rich layer believed to be zirconium oxide. Thermodynamic considerations indicate that the zirconium-rich layer formed first. The iron-oxide layer appears to have resulted from the diffusion of iron through the zirconium-rich layer to the oxide-vapor interface.

• Research Organization: Argonne National Lab., IL (US)
• Sponsoring Organization: US Department of Energy (US)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 768627
• Report Number(s): ANL/CMT/CP-103450
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
AUGER ELECTRON SPECTROSCOPY
CORROSION PRODUCTS
INTERMETALLIC COMPOUNDS
IRON ALLOYS
IRON OXIDES
OXIDATION
RADIONUCLIDE MIGRATION
STEAM
THERMODYNAMICS
TRANSMISSION ELECTRON MICROSCOPY
WASTE FORMS
ZIRCONIUM ALLOYS
ZIRCONIUM OXIDES