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Application of the TSPA Glass Degradation Model to Non-Conforming Waste Forms

Published online by Cambridge University Press:  17 March 2011

W. L. Ebert*
Affiliation:
Chemical Engineering Division, Argonne National Laboratory, Argonne, IL 60439, [email protected]
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Abstract

An approach is presented for determining if the models used to calculate the release of radionuclides from defense high-level radioactive waste (HLW) glass for total system performance assessment (TSPA) calculations can be used to account for the release of radionuclides from waste forms other than standard borosilicate glasses. The fractional release rates of radionuclides due to waste form degradation, the available surface area, and the radionuclide inventory in an alternative waste form can be compared with the corresponding models used in TSPA for HLW glasses to determine if those models adequately represent the waste form. This approach is demonstrated for the ceramic and metallic waste forms developed for electrometallurgically treated spent sodium-bonded nuclear fuel. Depending on the waste form, comparisons made with aspects of the HLW glass model may be based on similarities in degradation mechanisms or purely empirical.

Type
Research Article
Copyright
Copyright © Materials Research Society 2004

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References

1.Office of Civilian Radioactive Waste Management, “Waste Acceptance System Requirements Document,” Rev. 04, DOE/RW-0351, January 2002.Google Scholar
2.Office of Civilian Radioactive Waste Management, “Defense HLW Glass Degradation Model,” Bechtel SAIC Company report ANL-EBS-MD-000016 Rev 01 ICN 01 (February 2004).Google Scholar
3.Office of Civilian Radioactive Waste Management, “Radionuclide Inventory Model,” Bechtel SAIC Company report ANL-WIS-MD-000020 Rev 00 (November 2003).Google Scholar
4. Lewis, M.A.; Hash, M.C.; Hebden, A.; and Ebert, W.L. 2002. “Tests with Ceramic Waste Form Materials Made by Pressureless Consolidation,” Argonne National Laboratory report ANL-02/10. Argonne, Illinois: Argonne National Laboratory.Google Scholar
5. Morss, L.R.; Johnson, S.G.; Ebert, W.L.; DiSanto, T.; Frank, S.M.; Holly, J.L.; Kropf, A.J.; Mertz, C.J.; Noy, M.; O'Holleran, T.P.; Richmann, M.K.; Sinkler, W.; Tsai, Y.; and Warren, A.R., “Corrosion Tests with Uranium- and Plutonium-Loaded Ceramic Waste Forms,” Argonne National Laboratory report ANL-02/09. Argonne, Illinois: Argonne National Laboratory.Google Scholar
6. Fanning, T.H.; Ebert, W.L.; Frank, S.M.; Hash, M.C.; Morris, E.E.; Morss, L.R.; O'Holleran, T.P.; and Wigeland, R.A. “Status of Ceramic Waste Form Degradation and Radionuclide Release Modeling,” Argonne National Laboratory report ANL-03/8. Argonne, Illinois: Argonne National Laboratory.Google Scholar
7. Ebert, W. L., Lewis, M. A., Barber, T. L., and DiSanto, T., “Static Leach Tests with the EBR II Metallic Waste Form,” Argonne National Laboratory report ANL-03/29.Google Scholar
8. McDeavitt, S.M., Abraham, D.P., and Park, J.Y., “Evaluation of Stainless-Steel-Zirconium Alloys as High-Level Nuclear Waste Forms,” Journal of Nuclear Materials 257, 2134 (1998).Google Scholar