Assessment of Boiling Heat Transfer Correlations for Once-Through Steam Generators
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The steam generators provide a dynamic link between the reactor core and the turbine generator in pressurized-water-reactor (PWR) power plants and therefore play an important role in the safe and reliable operation of these plants. Modeling and prediction of the steam generator secondary side behavior during steady state and transients is essential for evaluating primary side response and heat sink capability. In this paper, a steady state simulation of a 19-tube model once-through steam generator was performed with the TRAC-PF1 thermal-hydraulic computer code. The predicted steady-state results were not in a 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 once-through steam generator analysis.
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