Horizontal Steam Generator Thermal-Hydraulics at Various Steady-State Power Levels

Conference · Mon Jul 01 00:00:00 EDT 2002

OSTI ID:21072858

Stevanovic, Vladimir D ^[1]; Stosic, Zoran V; Kiera, Michael; Stoll, Uwe ^[2]

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1. University of Belgrade, Kraljice Marije 16, 11000 Belgrade, Serbia and Montenegro (Yugoslavia)
2. Framatome ANP GmbH, P.O. Box 3220, 91050 Erlangen (Germany)

Three-dimensional computer simulation and analyses of the horizontal steam generator thermal-hydraulics of the WWER 1000 nuclear power plant have been performed for 50% and 75% partial loads, 100% nominal load and 110% over-load. Presented results show water and steam mass flow rate vectors, steam void fraction spatial distribution, recirculation zones, swell level position, water mass inventory on the shell side, and other important thermal-hydraulic parameters. The simulations have been performed with the computer code 3D ANA, based on the 'two-fluid' model approach. Steam-water interface transport processes, as well as tube bundle flow resistance, energy transfer, and steam generation within tube bundles are modelled with {sup c}losure laws{sup .} Applied approach implies non-equilibrium thermal and flow conditions. The model is solved by the control volume procedure, which has been extended in order to take into account the 3D flow of liquid and gas phase. The methodology is validated by comparing numerical and experimental results of real steam generator operational conditions at various power levels of the WWER Novovoronezh, Unit 5. One-dimensional model of the horizontal steam generator has been built with the RELAP 5 standard code on the basis of the multidimensional two-phase flow structure obtained with the 3D ANA code. RELAP 5 and 3D ANA code results are compared, showing acceptable agreement. (authors)

• Research Organization: The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
• OSTI ID: 21072858
• Resource Relation: Conference: ICONE-10: 10. international conference on nuclear engineering, Arlington - Virginia (United States), 14-18 Apr 2002; Other Information: Country of input: France
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
COMPUTER CODES
COMPUTERIZED SIMULATION
ENERGY TRANSFER
FLOW RATE
MASS
NUCLEAR POWER PLANTS
ONE-DIMENSIONAL CALCULATIONS
SPATIAL DISTRIBUTION
STEADY-STATE CONDITIONS
STEAM
STEAM GENERATION
STEAM GENERATORS
THERMAL HYDRAULICS
THREE-DIMENSIONAL CALCULATIONS
TUBES
TWO-PHASE FLOW
VOID FRACTION
WATER
WWER TYPE REACTORS