Dispersed-flow film boiling of high-pressure water in a rod bundle. [PWR]

Technical Report · Sun Aug 01 00:00:00 EDT 1982

OSTI ID:5083421

Morris, D G; Mullins, C B; Yoder, G L

The following six dispersed flow film boiling correlations were assessed using data from the third ORNL transient film boiling experiment (Test 3.08.6C) conducted in the THTF: Dougall-Rohsenow; Dougall-Rohsenow (with Prandtl number evaluated at the wall temperature, as used in RELAP4-MOD7); Groeneveld 5.9; Groeneveld 5.7; Groeneveld-Delorme; and Condie-Bengston IV. The correlations were evaluated with bundle fluid conditions calculated using a homogeneous two-phase flow and thermodynamic equilibrium thermal-hydraulics code. Comparisons made between experimentally determined heat transfer coefficients and the individual correlation's heat transfer coefficients indicate that the Dougall-Rohsenow correlations often overpredict the heat transfer coefficients, while the Groeneveld 5.7, Groeneveld 5.9, and Condie-Bengston IV correlations tend to be in good agreement with the data. The Groeneveld-Delorme correlation underpredicts the data.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5083421
• Report Number(s): NUREG/CR-2183; ORNL/TM-7864; ON: DE82020498
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOSS OF COOLANT
FILM BOILING
HEAT TRANSFER
HYDRAULICS
TEST FACILITIES
PWR TYPE REACTORS
COMPARATIVE EVALUATIONS
FUEL ASSEMBLIES
FUEL RODS
MATHEMATICAL MODELS
REACTOR SAFETY
TEMPERATURE GRADIENTS
ACCIDENTS
BOILING
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
MECHANICS
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled