Parametric study of boiling heat transfer in porous media

Conference · Mon Apr 01 04:00:00 EST 1996

OSTI ID:230563

Shi, B; Jones, B G ^[1]; Pan, C ^[2]

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1. Illinois Univ., Urbana, IL (United States). Dept. of Nuclear Engineering
2. National Tsing Hua Univ., Hsinchu (Taiwan, Province of China). Dept. of Nuclear Engineering

Detailed numerical modeling and parametric variation studies were conducted on boiling heat transfer processes in porous deposits with emphasis on applications associated with light water nuclear power reactor systems. The processes of boiling heat transfer in the porous corrosion deposits typically involve phase changes in finite volumetric regions in the porous media. The study examined such processes in two porous media configurations, without chimneys (homogeneous porous structures) and with chimneys (heterogeneous porous structures). A 1-D model and a 2-D model were developed to simulate two-phase flows with phase changes, without dry-out, inside the porous media for both structural configurations. For closure of the governing equations, an empirical correlation of the evaporation rate for phase changes inside the porous media was introduced. In addition, numerical algorithms were developed to solve the coupled nonlinear equations of mass, momentum, energy, capillary pressure, and evaporation rate. The distributions of temperature, thermodynamic saturation, liquid pressure, vapor pressure, liquid velocity, and vapor velocity were predicted. Furthermore, the effects of heat flux, system pressure, porosity, particle diameter, chimney population density, chimney radius, and crud thickness on the all superheat, critical heat flux, and minimum saturation were examined. The predictions were found to be in good agreement with the available experimental results.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 230563
• Report Number(s): ANL/RA/CP--89398; CONF-960306--29; ON: DE96008460
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
BOILING
CHIMNEYS
CORROSION PRODUCTS
DEPOSITS
HEAT FLUX
HEAT TRANSFER
NUCLEAR POWER PLANTS
PARTICLE SIZE
POROUS MATERIALS
PRESSURE DEPENDENCE
SUPERHEATERS
SUPERHEATING
THERMAL CONDUCTIVITY
THICKNESS
TWO-PHASE FLOW