Improved heat transfer correlation for steam generator bundles
- Additional Document Info
- View All
A RELAP5/MOD2 computer code model for a Once Through Steam Generator has been developed. Parametric studies were conducted. The calculated heat transfer in the nucleate boiling flow was underpredicted. Existing heat transfer correlations used in thermal-hydraulic computer codes do not provide accurate predictions of the measurement-derived secondary convective heat transfer coefficients. A new flow regime map for flow across bundles has been developed and implemented in the code. This new flow regime map predicts better transition criteria between bubbly-to-slug and slug-to-annular flow. Consequently, improved saturated conditions for the fluid flow at the entrance to the boiler were obtained. A new Chen-type correlation was developed to predict the boiling heat transfer for steam generator tube bundle geometries. This new correlation predicts better superheat.
author list (cited authors)
Hassan, Y. A., & Blanchat, T. K.