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Jason Chao, V. K. (Bindi) Chexal, William H. Layman, David A. Rautmann, Craig E. Peterson, Larry W. Cress
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 224-237
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33193
Articles are hosted by Taylor and Francis Online.
The RETRAN-02 and DYNODE-P thermal-hydraulic codes were compared against actual Prairie Island plant data from a steam generator tube break incident that occurred on October 2, 1979. The predictions from the code calculations compare well with actual plant behavior. The time of the break in the Prairie Island incident was found to be ∼260 s prior to scram with an initial break flow of 625 gal/min. Discharge coefficients are recommended for the calculations of critical flow from the break with extended Henry-Fauske and Moody critical flow models. In addition, a linear correlation was developed to predict the break flow with a given system depressurization rate for a Westinghouse two-loop plant.