Steady-state and transient prediction of a 19-tube once-through steam generator using RELAP5/MOD1

Journal Article · Sat Jan 01 04:00:00 EST 1983 · Nucl. Technol.; (United States)

OSTI ID:5552349

Hassan, Y A; Morgan, C D

Comparisons of the predictions of RELAP5/MOD1 to data obtained from a 19-tube model of a once-through steam generator (OTSG) were performed. The initial results were not satisfactory since the predicted outlet steam temperature was much too low. This discrepancy was traced to the inappropriate use of the modified Zuber critical heat flux (CHF) correlation for the conditions occurring during integral economizer OTSG operation. A study of available low-flow CHF correlations was performed that showed that either the Macbeth or Biasi correlations used in conjunction with RELAP5/MOD1 would produce good agreement with both the steadystate and transient data for the integral economizertype OTSG. The Macbeth correlation was the best for the OTSG with a recirculation path; however, it was not entirely satisfactory due to a slight delay in its prediction of CHF. A loss-of-feedwater transient was modeled using the Macbeth CHF correlation and compared to experimental data with satisfactory results.

• Research Organization: Babcock and Wilcox Company, Nuclear Power, Generation Division, P. O. Box 1260, Lynchburg, Virginia 24505
• OSTI ID: 5552349
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 60:1; ISSN NUTYB
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
420400* -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
BOILERS
COMPUTERIZED SIMULATION
CORRELATIONS
CRITICAL HEAT FLUX
ECONOMIZERS
HEAT FLUX
LOSS OF COOLANT
REACTOR ACCIDENTS
SIMULATION
STEADY-STATE CONDITIONS
STEAM GENERATORS
TRANSIENTS
TUBES
VAPOR GENERATORS