Overview of mineral waste form development for the electrometallurgical treatment of spent nuclear fuel
Conference
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OSTI ID:228502
Argonne is developing a method to treat spent nuclear fuel in a molten salt electrorefiner. Wastes from this treatment will be converted into metal and mineral forms for geologic disposal. A glass-bonded zeolite is being developed to serve as the mineral waste form that will contain the fission products that accumulate in the electrorefiner salt. Fission products are ion exchanged from the salt into the zeolite A structure. The crystal structure of the zeolite after ion exchange is filled with salt ions. The salt-loaded zeolite A is mixed with glass frit and hot pressed. During hot pressing, the zeolite A may be converted to sodalite which also retains the waste salt. The glass-bonded zeolite is leach resistant. MCC-1 testing has shown that it has a release rate below 1 g/(m{sup 2}day) for all elements.
- Research Organization:
- Argonne National Lab., IL (United States). Chemical Technology Div.
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 228502
- Report Number(s):
- ANL/CMT/CP--88394; CONF-9606116--23; ON: DE96010793
- Country of Publication:
- United States
- Language:
- English
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