Application of the TSPA glass degradation model to non-conforming waste forms.
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.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- NE
- DOE Contract Number:
- DE-AC02-06CH11357
- OSTI ID:
- 963258
- Report Number(s):
- ANL/CMT/CP-49695; TRN: US0903153
- Resource Relation:
- Conference: 2004 MRS Spring Meeting; Apr. 12, 2004 - Apr. 16, 2004; San Francisco, CA
- Country of Publication:
- United States
- Language:
- ENGLISH
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ACCOUNTING FOR A VITRIFIED PLUTONIUM WASTE FORM IN THE YUCCA MOUNTAIN REPOSITORY TOTAL SYSTEM PERFORMANCE ASSESSMENT (TSPA)
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