ASSESSMENT OF BOILING HEAT TRANSFER CORRELATIONS FOR ONCE-THROUGH STEAM GENERATORS. Academic Article

abstract

• A steady-state simulation of a 19-tube model once-thorough 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.

authors

• Hassan, Yassin

published proceedings

• Nuclear Technology

author list (cited authors)

• Hassan, Y. A.

citation count

• 1

complete list of authors

• Hassan, YA

publication date

• January 1988

published in

• Nuclear Technology  Journal

Digital Object Identifier (DOI)

• 10.13182/NT88-A16066

start page

• 446

end page

• 449

volume

• 81

issue

• 3