, Volume 49, Issue 7, pp 34–40 | Cite as

Ceramic-composite waste forms from the electrometallurgical treatment of spent nuclear fuel

  • C. Pereira
  • M. Hash
  • M. Lewis
  • M. Richmann
Processing Nuclear Waste Research Summary


Argonne National Laboratory is developing a method to treat spent nuclear fuel in a molten-salt electrorefiner. Glass-bonded zeolite and sodalite are both being developed as ceramic waste forms. The ceramic waste form will contain the fission product (e.g., rare earth, alkali and alkaline-earth metals, halogens, and chalcogens) and transuranic radionuclides that accumulate in the electrorefiner salt. Zeolite A can fully incorporate both the salt and the radionuclides into its crystal structure. Salt-loaded zeolite A is mixed with glass frit; the blend undergoes hot isostatic pressing to produce a monolithic leach-resistant waste form. Alternatively, the salt-loaded zeolite may be converted to sodalite simply by heat treating first, then adding the glass and hot pressing.


Zeolite Argonne National Laboratory Glass Frit Spend Nuclear Fuel Waste Form 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.


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Copyright information

© The Minerals, Metals & Materials Society 1997

Authors and Affiliations

  • C. Pereira
  • M. Hash
  • M. Lewis
  • M. Richmann

There are no affiliations available

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