Corrosion testing of stainless steel-zirconium metal waste forms Academic Article

abstract

• AbstractStainless 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.

authors

• Mcdeavitt, Sean

published proceedings

• SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXII

author list (cited authors)

• Abraham, D. P., Simpson, L. J., Devries, M. J., & McDeavitt, S. M.

citation count

• 9

complete list of authors

• Abraham, DP||Simpson, LJ||Devries, MJ||McDeavitt, SM

publication date

• December 1999

publisher

• Springer Nature  Publisher

published in

• MRS Online Proceedings Library  Journal

keywords

• 40 Engineering
• 4016 Materials Engineering
• 4018 Nanotechnology

Digital Object Identifier (DOI)

• 10.1557/PROC-556-945

start page

• 945

end page

• 952

volume

• 556

URL

• http%3A%2F%2Fdx.doi.org%2F10.1557%2Fproc-556-945

user-defined tag

• 12 Responsible Consumption and Production