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Leaching of Irradiated Candu UO2 Fuel

  • T. T. Vandergraaf
  • L. H. Johnson
  • D. W. P. Lau
Part of the Advances in Nuclear Science & Technology book series (ANST)

Abstract

An assessment of the concept to dispose of spent, irradiated nuclear fuel in an underground repository requires information on the rates of radionuclide leaching from the fuel matrix and of fuel matrix dissolution.

Keywords

Dissolution Rate Fuel Element Spend Fuel Waste Form Leach Rate 
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

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    L. J. Clegg and J. R. Coady, “Radioactive Decay Properties of CANDU Fuel, Volume 1,” The Natural Uranium Fuel Cycle, Atomic Energy of Canada Limited Report, AECL-4436/1 (1977).Google Scholar
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    W. B. Lewis, J. R. MacEwan, W. H. Stevens, and R. G. Hart, “Fission Gas Behavior in UO2 Fuel,” Proc. Third International Conference on Peaceful Uses of Atomic Energy, Geneva 1964 11, 405–415 (1965).Google Scholar
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    U. B. Ekland and R. Forsyth, Leaching of Irradiated UO2 Fuel, KBS Report 70, February (1978).Google Scholar
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    Y. B. Katayama, “Leaching of Irradiated LWR Fuel Pellets in Deionized and Typical Groundwater,” BNWL-2057 (1978).Google Scholar
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    D. E. Grandstaff, “A Kinetic Study of the Dissolution of Uranite,” Econ. Geol. 71, 1493–1505 (1976).CrossRefGoogle Scholar

Copyright information

© Springer Science+Business Media New York 1980

Authors and Affiliations

  • T. T. Vandergraaf
    • 1
  • L. H. Johnson
    • 1
  • D. W. P. Lau
    • 1
  1. 1.Whiteshell Nuclear Research EstablishmentAtomic Energy of Canada LimitedPinawaCanada

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