Advertisement

Thermal-Hydraulic Analysis of the Ginna Steam Generator Tube Rupture Event Using RETRAN-02

  • R. K. Wyrick
  • E. N. Winkler
  • W. W. Brown

Abstract

A detailed analysis of the thermal-hydraulic response of the R. E. Ginna nuclear power plant during a major steam generator tube rupture event of January 25, 1982, was performed. The event illustrated a number of thermal-hydraulic phenomena and operational problems that can occur during tube rupture transients. For this analysis, a computer simulation of the Ginna event was performed using the RETRAN-02 computer code (Ref. 1) and the results compared to the available plant data and sequence of events. The objectives of this analysis included the following:
  • a thorough understanding of the thermal-hydraulic response of a nuclear power plant during a steam generator tube rupture transient

  • better understanding of the sequence of events and physical phenomena that occurred during the Ginna event than was available from the plant data

  • better understanding of various procedural actions and their corresponding affect on the physical response of a nuclear power plant during steam generator tube rupture transients.

Keywords

Reactor Vessel Steam Generator Plant Data Safety Valve Steam Line 
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.
    “RETRAN-02, “A Program for Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems,” EPRI NP-1850-CCM, May, 1981.Google Scholar
  2. 2.
    Henry, R.E. and Fauske, H. K. “The Two-Phase Critical Flow of One-Component Mixtures in Nozzles, Orifices, and Short Tubes,“ J. Heat Transfer, 93, 179–187, 1971CrossRefGoogle Scholar
  3. 3.
    Moody, F. J., “Maximum Flow Rate of a Single Component, Two-Phase Mixture, J. Heat Transfer, 87, 134–142, 1965CrossRefGoogle Scholar
  4. 4.
    “Analysis of Steam Generator Tube Rupture Events at Oconee and Ginna,” INPO Report 82-030, November, 1982Google Scholar
  5. 5.
    “Thermal-Hydraulic Analysis of Ginna Steam Generator Tube Rupture Event”, INPO Report 83-, 1983Google Scholar
  6. 6.
    “Incident Evaluation, Ginna Steam Generator Tube Failure Incident, January 25, 1982, R. E. Ginna Nuclear Power Plant,” Rochester Gas and Electric Company, April 12, 1982Google Scholar
  7. 7.
    “NRC Report on the January 25, 1982, Steam Generator Tube Rupture at R. E. Ginna Nuclear Power Plant,” NUREG-0909, April 1982.Google Scholar

Copyright information

© Springer Science+Business Media New York 1984

Authors and Affiliations

  • R. K. Wyrick
    • 1
  • E. N. Winkler
    • 1
  • W. W. Brown
    • 1
  1. 1.Institute of Nuclear Power OperationsAtlantaUSA

Personalised recommendations