PORTHOS - A computer code for solving general three-dimensional, time-dependent two-fluid equations
Conference
·
OSTI ID:5746301
PORTHOS is a computer code for calculating three-dimensional steady-state or time dependent two-phase flow in porous or non-porous media. It was developed with the initial goal of simulating two-phase flows in steam generators of PWR nuclear power plants. However, the modular code design and the generality of approach allow application to a wide variety of problems in single phase or two-phase flow. The present method employs a finite difference technique to solve the complete set of two-fluid equations, i.e., the ''six-equation'' model which includes tow mass conservation equations, two momentum equations, two energy equations, as well as constitutive equations to effect closure of the system. The use of volume porosity and surface permeability allows the treatment of complex geometry. This paper describes the mathematical basis, the numerical solution procedure employed, and the results of comparisons with two sources of experimental data: the 8MW FRIGG loop experiment and the Electricite de France (EdF) Bugey 4 steam generator test. Calculations of the FRIGG experiment by PORTHOS, in terms of void fraction distribution, are in good agreement with measurements. Verification against the EdF data is also quite satisfactory.
- OSTI ID:
- 5746301
- Report Number(s):
- CONF-861211-
- Country of Publication:
- United States
- Language:
- English
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99 GENERAL AND MISCELLANEOUS
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BOILERS
BUGEY-4 REACTOR
COMPUTER CODES
COMPUTERIZED SIMULATION
DISTRIBUTION
ENRICHED URANIUM REACTORS
EQUILIBRIUM
FINITE DIFFERENCE METHOD
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
HEAT EXCHANGERS
HYDRAULICS
ITERATIVE METHODS
MATERIALS
MATHEMATICAL MODELS
MATRICES
MECHANICS
NUMERICAL SOLUTION
P CODES
PERMEABILITY
POROUS MATERIALS
POWER REACTORS
PWR TYPE REACTORS
REACTORS
SIMULATION
STEADY-STATE CONDITIONS
STEAM GENERATORS
TESTING
THREE-DIMENSIONAL CALCULATIONS
TIME DEPENDENCE
TUBES
TWO-PHASE FLOW
VALIDATION
VAPOR GENERATORS
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS