Two-Phase Flow Interfacial Drag for Once-Through Steam Generators Academic Article

abstract

• The current version of the RELAP5/MOD2 computer code underpredicts the degree of superheat in the secondary side of the steam generator bundles. Many studies have concluded that this is due to overprediction of the interphase drag force. New interphase drag correlations have been developed for the bubby and slug regimes. These correlations were implemented in the current version of the RELAP5/MOD2 computer code. Steady-state conditions for 65, 75, and 100% power loads of 30-tube once-through steam generator tests are simulated. The calculated primary-and secondary-side temperature profiles show that the new interphase drag correlations achieve closer agreement with experimental data than the temperature profiles of the original code.

authors

• Hassan, Yassin

published proceedings

• Nuclear Technology

author list (cited authors)

• Hassan, Y. A., & Rais, O.

citation count

• 4

complete list of authors

• Hassan, Yassin A||Rais, Omar

publication date

• July 1991

publisher

• Informa UK Limited  Publisher

published in

• Nuclear Technology  Journal

Digital Object Identifier (DOI)

• 10.13182/nt91-a34569

start page

• 77

end page

• 86

volume

• 95

issue

• 1

URL

• http://dx.doi.org/10.13182/nt91-a34569