Advertisement

JOM

, Volume 49, Issue 7, pp 29–32 | Cite as

Stainless steel-zirconium waste forms from the treatment of spent nuclear fuel

  • S. M. McDeavitt
  • D. P. Abraham
  • J. Y. Park
  • D. D. Keiser
Processing Nuclear Waste Research Summary

Abstract

Stainless steel-zirconium waste-form alloys have been developed for the disposal of metallic wastes recovered from spent nuclear fuel using the electrometallurgical process developed by Argonne National Laboratory. The metal waste comprises the spent-fuel cladding, noble-metal fission products, and other metallic constituents remaining after electrorefining. Two nominal waste-form compositions have been slected: stainless steel-clad fuels and zirconium-8 wt.% stainless steel for Zircaloy-clad fuels. These alloys are very corrosion resistant. Tests performed with these alloys indicate favorable behavior for use high-level nuclear waste forms.

Keywords

Corrosion Rate Argonne National Laboratory Spend Nuclear Fuel Waste Form Fuel Treatment 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

References

  1. 1.
    C.C. McPheeters et al., “Electrometallurgically Treating Metal, Oxide, and Al-Alloy Spent Nuclear Fuel,”JOM, 49(7) (1997), pp. 22–25.CrossRefGoogle Scholar
  2. 2.
    J.P. Ackerman et al., “Isolating Wastes in the Electrometallurgical Treatment of Spent Nuclear Fuel,”JOM, 49 (7) (1997), pp. 26–28.CrossRefGoogle Scholar
  3. 3.
    C. Pereira et al., “Ceramic Composite Waste Forms from the Electrometallurgical Treatment of Spent Nuclear Fuel,”JOM, 49 (7) (1997), 34–37.CrossRefGoogle Scholar
  4. 4.
    M.A. Lewis, D.F. Fischer, and C.D. Murphy, “Densification of Salt-Occluded Zeolite A Powders to a Leach Resistant Monolith”Scientific Basis for Nuclear Waste Management, ed. A. Barkatt and R. Van Koynenburg. (Pittsburgh, PA: MRS, 1994), p. 95.Google Scholar
  5. 5.
    S.M. McDeavitt, J.Y. Park, and J.P. Ackerman, “Defining a Metal-Based Waste Form for IFR Pyroprocessing Wasters,”Actinide Processing: Methods and Materials, ed. B. Mishra and W.A. Averill (Warrendale, PA: TMS, 1994), pp. 305–319.Google Scholar
  6. 6.
    D.P. Abraham, S.M. McDeavitt, and J.Y. Park, “Microstructure and Phase Identification in Type 304 Stainless Steel-Zirconium Alloys,”Metall. Mater. Trans. A, 27A (1996), pp. 2151–2159.CrossRefGoogle Scholar
  7. 7.
    S.M. McDeavitt et al., “Stainless Steel-Zirconium Alloy Waste Forms for Metallic Fission Products and Actinides Isolated During Treatment of Spent Nuclear Fue,”International Topical Meeting on Nuclear and Hazardous Waste Management, (LaGrange Park, IL, ANS, 1996), pp. 2477–2484.Google Scholar
  8. 8.
    S.M. McDeavitt et al., “Alloy Waste Forms for Metallic Fission Products and Actinides Isolated by Spent Nuclear Fuel Treatment,”Extraction and Processing for the Treatment and Minimization of Wastes (Warrendale, PA: TMS, 1996), pp. 177–189.Google Scholar
  9. 9.
    D.P. Abraham, S.M. McDeavitt, and J.Y. Park, “Metal Waste Forms from the Electrometallurgical Treatment of Spent Nuclear Fuel,”DOE Spent Nuclear Fuel & Fissile Material Management (LaGrange Park, IL: ANS, 1996), pp. 123–128.Google Scholar
  10. 10.
    B.R. Westphal et al., “Production of Metal Waste Forms from Spent Fuel Treatment,”DOE Spent Nuclear Fuel Challenges and Initiatives (LaGrange Park, IL: ANS, 1994), p. 288.Google Scholar
  11. 11.
    D.P. Abraham, J.W. Richardson, and S.M. McDeavitt, “Formation of the Fe23Zr6 Phase in an Fe−Zr Alloy,”Scr. Mater. J., in press.Google Scholar

Copyright information

© The Minerals, Metals & Materials Society 1997

Authors and Affiliations

  • S. M. McDeavitt
  • D. P. Abraham
  • J. Y. Park
  • D. D. Keiser

There are no affiliations available

Personalised recommendations