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High-Level Waste Vitrification Product Characterization

  • G. H. Bryan
  • W. J. Bjorklund
  • W. L. Kuhn
Part of the Advances in Nuclear Science & Technology book series (ANST)

Abstract

The Nuclear Waste Vitritication Project (NWVP) was conducted to provide a demonstration of the vitrification of high-level liquid waste (HLLW) from spent fuel discharged from an operating LWR.

Keywords

Waste Form Heat Generation Rate Waste Glass Glass Density Gamma Measurement 
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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References

  1. 1.
    J. L. McElroy, K. J. Schneider, J. H. Hartley, J. E. Mendel, G. L. Richardson, R. W. McKeen and A. G. Blasewitz, Waste Solidification Program Summary Report, Vol. II, BNWL-1667, Battelle-Pacific Northwest Laboratory, Richland, WA 99342, (1972).Google Scholar
  2. 2.
    E. J. Wheelwright, W. J. Bjorklund, L. M. Browne, G. H. Bryan, L. K. Holton, E. R. Irish, D. H. Siemens, Technical Summary-Nuclear Waste Vitrification Project, PNL-3038, Battelle-Pacific Northwest Laboratory, Richland, WA 99352, (1979).Google Scholar
  3. 3.
    J. E. Mendel, Annual Report on the Characteristics of High-Level Waste Glass, BNWL-2252, Battelle-Pacific Northwest Laboratory, Richland, WA 99352, (1977).Google Scholar

Copyright information

© Springer Science+Business Media New York 1980

Authors and Affiliations

  • G. H. Bryan
    • 1
  • W. J. Bjorklund
    • 1
  • W. L. Kuhn
    • 1
  1. 1.Pacific Northwest LaboratoryRichlandUSA

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