Convection-radiation heat transfer to steam in rod bundle geometry/

Journal Article · Sat Dec 01 04:00:00 EST 1984 · Nucl. Technol.; (United States)

OSTI ID:6056516

Sozer, A; Anklam, T M; Dodds, H L

An engineering heat transfer model was developed to predict the total heat transfer coefficients above the froth region in a nuclear reactor core undergoing a slow core uncovering. The model consists of a new heat transfer correlation for convection to steam and a one-dimensional thermal radiation equation. Above the froth region, large wall-to-bulk temperature ratios can take place; therefore, variable property effects on flow and heat transfer were examined because they can affect the heat transfer conditions to a considerable extent. The convective heat transfer coefficients and rod surface temperatures were calculated by using various correlations. The comparison of the results showed that the new correlation accurately predicts the convective heat transfer coefficients and, when combined with the radiation equation, the wall temperatures. The use of this model should be of value in modeling small-break loss-of-coolant accidents and preliminary design work.

• Research Organization: University of Tennessee, Nuclear Engineering Department Knoxville, Tennessee 37996
• OSTI ID: 6056516
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 67:3; ISSN NUTYB
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CONVECTION
DESIGN
ENERGY TRANSFER
EQUATIONS
FLOW MODELS
HEAT TRANSFER
LOSS OF COOLANT
MASS TRANSFER
MATHEMATICAL MODELS
ONE-DIMENSIONAL CALCULATIONS
RADIANT HEAT TRANSFER
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
ROD BUNDLES
STEAM
TEMPERATURE DEPENDENCE