Home / Publications / Journals / Nuclear Technology / Volume 76 / Number 2
Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 290-302
Fourth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33882
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A RETRAN-02 analysis was performed for a loss-of-feedwater transient without scram for a Westinghouse four-loop plant with Series 51 steam generators. A goal of this study was to use the same plant parameters that were used by Westinghouse in a report issued in December 1979. The primary differences in results from the two studies can be attributed to differences in the two methodologies. Sensitivity of the primary pressure response to steam generator nodalization, turbine trip time, moderator reactivity feedback coefficients, and Doppler reactivity coefficients was also studied.