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Corrosion Testing of Stainless Steel-Zirconium:Metal Waste Forms

Published online by Cambridge University Press:  10 February 2011

D. P. Abraham ,
L. J. Simpson ,
M. J. Devries  and
S. M. Mcdeavitt
D. P. Abraham
Affiliation:
Chemical Technology Division, Argonne National Laboratory, Argonne, IL 60439
L. J. Simpson
Affiliation:
Chemical Technology Division, Argonne National Laboratory, Argonne, IL 60439
M. J. Devries
Affiliation:
Chemical Technology Division, Argonne National Laboratory, Argonne, IL 60439
S. M. Mcdeavitt
Affiliation:
Chemical Technology Division, Argonne National Laboratory, Argonne, IL 60439
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Abstract

Stainless steel-zirconium (SS-Zr) alloys have been developed as waste forms for the disposal of metallic waste generated during the electrometallurgical treatment of spent nuclear fuel. The waste forms incorporate irradiated cladding hulls, components of the alloy fuel, noble metal fission products, and actinide elements. The baseline waste form is a stainless steel- 15 wt% zirconium (SS-15Zr) alloy. This article presents microstructures and some of the corrosion studies being conducted on the waste form alloys. Electrochemical corrosio n, immersion corrosion, and vapor hydration tests have been performed on various alloy compositions to evaluate corrosion behavior and resistance to selective leaching of simulated fission products. The SS-Zr waste forms immobilize and retain fission products very effectively and show potential for acceptance as high-level nuclear waste forms.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 556: Symposium QQ – Scientific Basis for Nuclear Waste Management XXII , 1999 , 945
Copyright
Copyright © Materials Research Society 1999

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References

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