Hostname: page-component-77c89778f8-cnmwb Total loading time: 0 Render date: 2024-07-18T10:56:41.701Z Has data issue: false hasContentIssue false

Depleted Uranium Dioxide Waste Package for Spent Nuclear Fuel

Published online by Cambridge University Press:  21 March 2011

Charles W. Forsberg
Affiliation:
Oak Ridge National Laboratory Oak Ridge, TN 37831-6179, U.S.A.
Leslie R. Dole
Affiliation:
Oak Ridge National Laboratory Oak Ridge, TN 37831-6179, U.S.A.
Get access

Abstract

Depleted uranium dioxide (DUO2) waste packages (WPs) for disposal of spent nuclear fuel (SNF) are being investigated to (1) reduce radionuclide releases from WPs, (2) decrease the potential for repository nuclear criticality events, (3) provide radiation shielding, and (4) provide a means to beneficially use excess depleted uranium (DU). The DUO2 is incorporated into the WP as (1) a particulate fill for void spaces within the package and (2) a component of a DUO2-steel cermet (DUO2 embedded in steel) that replaces the steel components of the WP. Depending upon the design, there is 3 to 8 times as much DUO2 as SNF UO2 in the WP. Most radionuclides in the SNF cannot be released until the UO2 crystal structure is destroyed. The DUO2 surrounding the SNF slows the degradation of the SNF UO2 in the interior. This behavior is similar to the mechanisms that slow the degradation of natural uranium ore bodies containing UO2. The results of initial investigations and the expected thermodynamic WP behavior are described.

Type
Research Article
Copyright
Copyright © Materials Research Society 2002

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

1. Owen, J., Potential Disposal of Depleted Uranium in the YMP Subsurface Repository, Yucca Mountain Project, U.S. Department of Energy, Las Vegas, Nevada, July 27, 1999.Google Scholar
2. Leeds, E. J., “Comments on DUF6 Materials Use Roadmap,” Dated September 1, 2000, Letter to the U.S. Department of Energy from the U.S. Nuclear Regulatory Commission, ML003762080, NRC Public Reading Room, Bethesda, Maryland. October 18, 2000.Google Scholar
3. Forsberg, C. W., Nucl. Technol. 131, 252 (September 2000).Google Scholar
4. Forsberg, C. W., Shappert, L. B., Byrne, P., and Broadhead, B., “Cermet Transport, Storage, and Disposal Packages Using Depleted Uranium Dioxide and Steel,” Proc. 13th Inter. Symp. on the Packaging and Transport of Radioactive Materials, Chicago, Illinois, Institute of Nuclear Materials Management, September 2001.Google Scholar
5. Keller, D. L. in Reactor Handbook, 2nd ed., vol. 1, ed. by Tipton, C. R. Jr, . (Wiley Interscience, New York, 1960) pp. 304330.Google Scholar
6. U.S. Department of Energy, “Total System Performance Assessment-Viability Assessment Analysis Technical Basis Document,” B00000000-01717-4301-00006, Rev. 01, 1998.Google Scholar
7. Rechard, R., “Dissolved Concentration Component of Waste form Model in TSPA-SR,” in 2001 International High-Level Radioactive Waste Management Conference, Las Vegas, Nevada, April 29–May 3, 2001, American Nuclear Society, La Grange Park, Illinois, May 2001.Google Scholar
8. Crosthwaite, J. L., The Performance, Assessment, and Ranking of Container Design Options for the Canadian Nuclear Fuel Waste Management Program, COG-93-410, Atomic Energy of Canada Limited 1994.Google Scholar