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Title: Corrosion testing of stainless steel-zirconium metal waste form.

Abstract

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.

Authors:
Publication Date:
Research Org.:
Argonne National Lab., IL (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
11179
Report Number(s):
ANL/CMT/CP-97942
TRN: US0104338
DOE Contract Number:  
W-31109-ENG-38
Resource Type:
Conference
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
Subject:
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

Citation Formats

Abraham, D P. Corrosion testing of stainless steel-zirconium metal waste form.. United States: N. p., 1998. Web.
Abraham, D P. Corrosion testing of stainless steel-zirconium metal waste form.. United States.
Abraham, D P. 1998. "Corrosion testing of stainless steel-zirconium metal waste form.". United States. https://www.osti.gov/servlets/purl/11179.
@article{osti_11179,
title = {Corrosion testing of stainless steel-zirconium metal waste form.},
author = {Abraham, D P},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/11179}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Dec 14 00:00:00 EST 1998},
month = {Mon Dec 14 00:00:00 EST 1998}
}

Conference:
Other availability
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