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.
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References
Safety Code Development Group, “TRAC PF1, An Advanced Best-Estimate Computer Program for Pressurized Water Reactor Analysis,” Los Alamos National Laboratory report (in preparation).
“Final Safety Analysis Report, Oconee Nuclear Station, Units 1, 2 and 3,” Duke Power Co. (May 1969).
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).
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© 1984 Springer Science+Business Media New York
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Henninger, R.J., Ireland, J.R., DeMuth, N.S. (1984). Small-Break LOCA Recovery in B&W Plants. In: Lassahn, P.L., Majumdar, D., Brockett, G.F. (eds) Anticipated and Abnormal Plant Transients in Light Water Reactors. Springer, Boston, MA. https://doi.org/10.1007/978-1-4684-4799-6_64
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DOI: https://doi.org/10.1007/978-1-4684-4799-6_64
Publisher Name: Springer, Boston, MA
Print ISBN: 978-1-4684-4801-6
Online ISBN: 978-1-4684-4799-6
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