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Small-Break LOCA Recovery in B&W Plants

  • R. J. Henninger
  • J. R. Ireland
  • N. S. DeMuth

Abstract

A break of approximately 0.0012 m2 in the cold leg of a B&W plant results in an interruption of natural circulation when steam accumulates in the hot-leg U-bend. A small-break loss-of-coolant accident of this size was simulated by TRAC-PF1 to evaluate strategies for recovery and for re-establishing natural circulation. In the absence of operator action, core cooling occurs when water supplied by the high-pressure-injection system boils, then is discharged through the break. Raising the steam-generator secondary level, venting steam from the steam-generator secondary, venting steam from the hot-leg U-bend, “bumping” the reactor-coolant pumps, and injecting a portion of the high-pressure-injection system into the hot-leg U-bend aided in cooling and depressurizing the primary system but were ineffective in reestablishing natural-circulation flows in the primary-coolant loops.

Keywords

Steam Generator Primary System Natural Circulation Vent Valve Warm Fluid 
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.
    Safety Code Development Group, “TRAC PF1, An Advanced Best-Estimate Computer Program for Pressurized Water Reactor Analysis,” Los Alamos National Laboratory report (in preparation).Google Scholar
  2. 2.
    “Final Safety Analysis Report, Oconee Nuclear Station, Units 1, 2 and 3,” Duke Power Co. (May 1969).Google Scholar
  3. 3.
    J. R. Ireland and R. J. Henninger, “Analyses of B&W Small-Break LOCA TRAC Calculations”, Los Alamos National Laboratory report LA-UR-82-3294 (November 1982).Google Scholar

Copyright information

© Springer Science+Business Media New York 1984

Authors and Affiliations

  • R. J. Henninger
    • 1
  • J. R. Ireland
    • 1
  • N. S. DeMuth
    • 1
  1. 1.Energy DivisionLos Alamos National LaboratoryLos AlamosUSA

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