Corrosion testing of stainless steel-zirconium metal waste form.

Conference · Mon Dec 14 00:00:00 EST 1998

OSTI ID:11179

Abraham, D P

Stainless steel-zirconium (SS-Zr) alloys are being considered as waste forms for the disposition of metallic waste generated during the electrometallurgical treatment of spent nuclear fuel. The waste forms contain 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 microstructure and some of the corrosion studies being conducted on the waste form alloys. Electrochemical corrosion, 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 are successful at the immobilization and retention of fission products and show potential for acceptance as high-level nuclear waste forms.

• Research Organization: Argonne National Lab., IL (US)
• Sponsoring Organization: US Department of Energy (US)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 11179
• Report Number(s): ANL/CMT/CP-97942; TRN: US0104338
• Resource Relation: Conference: Materials Research Society 1998 Fall Meeting, Boston, MA (US), 11/29/1998--12/04/1998; Other Information: PBD: 14 Dec 1998
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
CORROSION RESISTANCE
ELECTROCHEMICAL CORROSION
HIGH-LEVEL RADIOACTIVE WASTES
MATERIALS TESTING
WASTE FORMS
ZIRCONIUM ALLOYS
STAINLESS STEELS
MICROSTRUCTURE
LEACHING
RADIOACTIVE WASTE DISPOSAL