Confirmation of the Ceramic Waste Form Degradation and Radionuclide Release Model
- Argonne National Laboratory (ANL), Argonne, IL (United States). Nuclear Engineering Division
A degradation and radionuclide release model had been previously created for the ceramic waste form that is being developed as part of the Spent Fuel Treatment Program at Argonne National Laboratory. During the last three years, numerous tests have been conducted to evaluate the performance of the ceramic waste form under conditions and with materials different from those used to create the model. This report compares model predictions with results of these tests to confirm that the model parameters are applicable to a wide range of conditions. In particular, tests conducted under repository-relevant temperatures and groundwater conditions are adequately predicted or bound by the model parameters. Finally, the performance of the CWF, as defined by the model, is shown to be better than the performance of defense high-level waste glass as modeled in the Total System Performance Assessment for the Site Recommendation of the Yucca Mountain repository.
- Research Organization:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 1551360
- Report Number(s):
- 730; ANL-NT--225; GNEP-AFCI-IMPT-PM-MS-2004-000040
- Country of Publication:
- United States
- Language:
- English
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