Published 1999 | Version v1
Book

Corrosion testing of stainless steel-zirconium metal waste forms

Description

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 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 immobilize and retain fission products very effectively and show potential for acceptance as high-level nuclear waste forms

Additional details

Publishing Information

Publisher
Materials Research Society
Imprint Place
Warrendale, PA (United States)
ISBN
1-55899-462-9
Imprint Title
Scientific basis for nuclear waste management XXII. Materials Research Society symposium proceedings: Volume 556
Imprint Pagination
1355 p.
Journal Page Range
p. 945-952
ISSN
0272-9172

Conference

Title
1998 Materials Research Society Fall Meeting
Dates
30 Nov - 4 Dec 1998
Place
Boston, MA (United States)

Optional Information

Contract/Grant/Project number
W-31109-ENG-38
Notes
Imprint:Single article reprints are available from University Microfilms Inc., 300 North Zeeb Road, Ann Arbor, Michigan 48106