Analysis of transient film boiling of high-pressure water in a rod bundle. [PWR]

Technical Report · Mon Mar 01 04:00:00 EST 1982

OSTI ID:5330166

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

The following six dispersed-flow film-boiling correlations were assessed using data from three ORNL transient film-boiling experiments 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. Equilibrium bundle fluid conditions are reported along with fuel rod simulator surface temperature and heat flux. Calculated experimental heat transfer coefficients are also reported. Uncertainties are reported for calculated heat transfer parameters for one of the transient tests. Thermodynamic nonequilibrium in the three transient tests was examined with an advanced two-fluid thermal-hydraulics code.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5330166
• Report Number(s): NUREG/CR-2469; ORNL/NUREG-85; ON: DE82013953
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210700 -- Nuclear Power Plants-- Regulation & Licensing
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BOILING
COMPARATIVE EVALUATIONS
ENERGY TRANSFER
FILM BOILING
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL MODELS
MECHANICS
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
SAFETY
TEST FACILITIES
TRANSIENTS
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS