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Dilute Chemical Decontamination Program Review

  • L. D. Anstine
  • J. C. Blomgren
  • P. J. Pettit

Abstract

It is desirable to reduce radiation exposure to workers in nuclear power plants to values that are as low as reasonably achievable. One method of reducing occupational exposure is to reduce the source of the exposure. Decontamination of the primary coolant system would reduce shutdown radiation levels and occupational radiation exposure in nuclear power plants.

Keywords

Dissolution Rate Oxalic Acid Nuclear Power Plant Corrosion Product Martensitic Stainless Steel 
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.
    P. J. Pettit, J. E. LeSurf, W. B. Stewart, R. J. Strickert, and S. B. Vaughan: “Decontamination of the Douglas Point Reactor by the Can-Decon Process,” presented at National Association of Corrosion Engineers Conference, Corrosion/78, Houston, Texas, March 1978.Google Scholar
  2. 2.
    L. D. Anstine: “BWR Decontamination and Corrosion Product Characterization,” General Electric Report NEDE-12665 (1977).Google Scholar
  3. 3.
    G. Romeo: “Characterization of Corrosion Product on Recirculation and Bypass Lines at Millstone-1,” General Electric Report NEDO-12680 (1978); EPRI NP-949 (1978).Google Scholar
  4. 4.
    L. D. Anstine and G. E. Von Nieda: “Characterization of the Corrosion Product Films on the Dresden-1 Decontamination Pilot Loop After Re-Exposure to Reactor Water,” General Electric Report NEDC-12691 (1977).Google Scholar

Copyright information

© Plenum Press, New York 1980

Authors and Affiliations

  • L. D. Anstine
    • 1
  • J. C. Blomgren
    • 1
  • P. J. Pettit
    • 1
  1. 1.General Electric Company, Commonwealth Edison Company and U.S. Department of EnergyUSA

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