Advertisement

Processing of High-Temperature Simulated Waste Glass in a Continuous Ceramic Melter

  • S. M. Barnes
  • R. A. Brouns
  • M. S. Hanson
Part of the Advances in Nuclear Science & Technology book series (ANST)

Abstract

The processing of spent nuclear fuel for defense and commercial purposes has generated a volume of high level liquid waste, which is being retained in storage tanks. The Pacific Northwest Laboratory (PNL), operated by the Battelle Memorial Institute under its contract with the Department of Energy, is developing suitable solidification processes for these and other radioactive wastes.

Keywords

Spend Nuclear Fuel Waste Glass Flux Agent High Level Liquid Waste Nuclear Waste Management 
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.

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

References

  1. 1.
    J. L. Buelt, “A Review of Continuous Ceramic-Lined Melters and Associated Experience at PNL,” Ceramics in Nuclear Waste Management CNF-790420, Technical Information Center, U. S. Dept. of Energy, Spring Field, VA, 107–113 (1979). Google Scholar
  2. 2.
    C. C. Chapman, J. L. Buelt, The Use of a Continuous Melter in Immobilization of Radioactive Defense Waste,“ Presented at the American Nuclear Society Meeting in San Diego, CA, June 1978, PNL-SA-6867, Pacific Northwest Laboratory, Richland, WA (1978). Google Scholar
  3. 3.
    J. M. Rusin, “Alternative Waste Forms-A Comparative Study,” Presented at the Materials Research Society Annual Meeting in Cambridge, MA, November 1979, PNL-SA-7769, Pacific Northwest Laboratory, Richland, WA (1979).Google Scholar
  4. 4.
    J. L. Buelt, “Liquid-Fed Ceramic Melter,” Quarterly Progress Report-Research and Development Activities - High Level Waste ImmobilizationProgram: April through June 1979 (J. L. McElroy, ed. PNL-3050–2 Pacific Northwest Laboratory, Richland, WA, in press). Google Scholar
  5. 5.
    C. C. Chapman, Vitrification of Hanford Wastes in a Joule-Heated Ceramic Melter and Evaluation of Resultant Canisterized Product, PNL-2904, Pacific Northwest Laboratory, Richland, WA (1979).CrossRefGoogle Scholar
  6. 6.
    M. J. Kupfer, Vitrification of Hanford Radioactive Defense Wastes, RHO-SA-89, Rockwell Hanford Operations, Richland, WA (1979).Google Scholar
  7. 7.
    W. Lutze, “Characterization of Glass and Glass Ceramic Nuclear Waste Forms,” Proc. of Symp. on Science Underlying Radioactive Waste Management Materials Research Society Annual Meeting Vol. 1, (G. J. McCarthy, ed., Plenum Press, New York, NY, 1979 ).Google Scholar

Copyright information

© Springer Science+Business Media New York 1980

Authors and Affiliations

  • S. M. Barnes
    • 1
  • R. A. Brouns
    • 1
  • M. S. Hanson
    • 1
  1. 1.Chemical TechnologyPacific Northwest LaboratoryRichlandUSA

Personalised recommendations