Simulation of three-dimensional hydrodynamic components with a one-dimensional transient analysis code

Conference · Mon Jan 01 04:00:00 EST 1990

OSTI ID:6892144

Shaw, R A ^[1]; Davis, C B ^[2]

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1. Los Alamos National Lab., NM (USA)
2. EG and G Idaho, Inc., Idaho Falls, ID (USA)

The RELAP5 series of transient analysis codes was developed to provide the United States Nuclear Regulatory Commission with a fast-running and user convenient reactor analysis tool. Although it was developed primarily for best-estimate transient simulation of pressurized water reactors, it has been used to simulate a wide spectrum of hydraulic and thermal transients in both nuclear and non-nuclear systems involving steam-water-noncondensible fluid mixtures. In recent years it has also been applied to thermal-hydraulic analyses of various US Department of Energy production reactors. RELAP5 is a one-dimensional code, meaning that the basic field equations are solved only in the axial direction of a component. Thus, for example, only axial flow is calculated in a reactor vessel; radial and azimuthal flows are not considered. This has been a minor limitation of the code because most hydraulic situations in reactor systems can be modeled adequately with a one-dimensional code. In those situations where three-dimensional flows were anticipated, the TRAC-PF1 code has generally been used. (TRAC-PF1 has the capability to model three-dimensional components; however, that option is normally only used in the reactor vessel model.) This paper describes the RELAP5 hexagonal model of the SRS L-Reactor as well as comparisons of benchmark calculations with SRS data. Emphasis is placed on the multidimensional phenomena. 6 refs., 6 figs.

• Research Organization: Los Alamos National Lab., NM (USA)
• Sponsoring Organization: NRC
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 6892144
• Report Number(s): LA-UR-90-1833; CONF-901101--3; ON: DE90012059
• Country of Publication: United States
• Language: English

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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99 GENERAL AND MISCELLANEOUS
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ACCIDENTS
ASYMMETRY
BOUNDARY CONDITIONS
COMPARATIVE EVALUATIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINERS
COOLING SYSTEMS
DISPERSIONS
ENERGY SYSTEMS
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
HEAVY WATER MODERATED REACTORS
HYDRODYNAMICS
L REACTOR
LAYERS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
MIXTURES
NATIONAL ORGANIZATIONS
PIPES
PRESSURE EFFECTS
PRODUCTION REACTORS
PUMPS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR VESSELS
REACTORS
SAVANNAH RIVER PLANT
SIMULATION
SPECIAL PRODUCTION REACTORS
T CODES
THERMODYNAMICS
THREE-DIMENSIONAL CALCULATIONS
TRANSIENTS
TWO-PHASE FLOW
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS