Home / Publications / Journals / Nuclear Technology / Volume 81 / Number 3
Nuclear Technology / Volume 81 / Number 3 / June 1988 / Pages 446-449
Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A16066
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A steady-state simulation of a 19-tube model once-through steam generator (OTSG) was performed with the TRAC-PF1 thermal-hydraulic computer code. The predicted steady-state results were not in good agreement with the experimental data. Underprediction of the observed superheat temperature was obtained. The current safety analysis computer programs use the Chen correlation. A modification in the Chen boiling correlation produced satisfactory results for use in OTSG analysis.