Degradation modeling of the ANL ceramic waste form
A ceramic waste form composed of glass-bonded sodalite is being developed at Argonne National Laboratory (ANL) for immobilization and disposition of the molten salt waste stream from the electrometallurgical treatment process for metallic DOE spent nuclear fuel. As part of the spent fuel treatment program at ANL, a model is being developed to predict the long-term release of radionuclides under repository conditions. Dissolution tests using dilute, pH-buffered solutions have been conducted at 40, 70, and 90 C to determine the temperature and pH dependence of the dissolution rate. Parameter values measured in these tests have been incorporated into the model, and preliminary repository performance assessment modeling has been completed. Results indicate that the ceramic waste form should be acceptable in a repository environment.
- Research Organization:
- Argonne National Laboratory, Argonne, IL (US)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 752872
- Report Number(s):
- ANL/RA/CP-100430; TRN: US0003117
- Resource Relation:
- Conference: ANS 4th Topical Meeting - DOE Spent Nuclear Fissile Material Management, San Diego, CA (US), 06/04/2000--06/08/2000; Other Information: PBD: 28 Mar 2000
- Country of Publication:
- United States
- Language:
- English
Similar Records
Status of ceramic waste form degradation and radionuclide release modeling.
Alternative Technical Summary Report: Electrometallurgical Treatment Variant