Evaluation and review of alternative waste forms for immobilization of high level radioactive wastes. Report number 3
A discussion of the relative strengths and weaknesses of the alternative forms and recommendations for future program directions are presented in the body of this report. In addition to the relative ranking, the Peer Review Panel makes the following observations and recommendations: (1) Differences in overall performance of most of the uncoated waste forms are relatively small when compared under approximately equivalent conditions. (2) The increased scientific basis for this class of waste forms has not yet been sufficient to achieve reliably large improvements in waste form performance over the best borosilicate glasses. (3) The increased leach rates at elevated temperatures and the uncertainty regarding mechanisms of leaching under repository conditions continue to indicate that surface temperatures of waste canisters and especially any waste form-water interfaces should be restricted to less than 100/sup 0/C, until more data is available to indicate otherwise. (4) Improvements are noteworthy, but there is still a need for adopting additional standardized tests, standard reference materials, common units and standardized methods of data presentation in the nuclear waste program. (5) Comparative data on leach rates in waters equilibrated with candidate rocks and potential geologic environments are almost non-existent and are essential to establish relevant long term extrapolation of waste form performance.(6) Understanding radiation damage effects on the microstructure and leaching mechanisms of polycrystalline ceramics is still insufficient to judge long term reliability of this class of waste forms. (7) More extensive data on rates and mechanisms of leaching of all waste forms under radiation and repository conditions are needed. (8) Additional studies of fundamental mechanisms controlling long term reliability of glass and alternative waste forms are strongly encouraged.
- Research Organization:
- Department of Energy, Washington, DC (USA). Office of Nuclear Waste Management
- OSTI ID:
- 6319956
- Report Number(s):
- DOE/TIC-11472; ON: DE81026323; TRN: 81-013775
- Country of Publication:
- United States
- Language:
- English
Similar Records
Development of a technical approach for assessing environmental release and migration characteristics of Hanford Grout
Ancient Glass: A Literature Search and its Role in Waste Management
Related Subjects
36 MATERIALS SCIENCE
BOROSILICATE GLASS
COMPARATIVE EVALUATIONS
CERAMICS
CONCRETES
GLASS
SILICON CARBIDES
SILICON OXIDES
SPRAY COATING
SYNTHETIC ROCKS
DATA ANALYSIS
LEACHING
MATERIALS
METALS
PLASMA ARC SPRAYING
RADIOACTIVE WASTE PROCESSING
SOLIDIFICATION
BUILDING MATERIALS
CARBIDES
CARBON COMPOUNDS
CHALCOGENIDES
DEPOSITION
DISSOLUTION
ELEMENTS
MANAGEMENT
OXIDES
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PROCESSING
ROCKS
SEPARATION PROCESSES
SILICON COMPOUNDS
SURFACE COATING
SYNTHETIC MATERIALS
WASTE MANAGEMENT
WASTE PROCESSING
052001* - Nuclear Fuels- Waste Processing
360204 - Ceramics
Cermets
& Refractories- Physical Properties
360603 - Materials- Properties