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

Conference · Mon Jan 01 04:00:00 EST 1990 · Transactions of the American Nuclear Society; (USA)

OSTI ID:5789169

Shaw, R A ^[1]; Davis, C B

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1. Los Alamos National Lab., NM (USA)

The RELAP5/MOD2 code is a fast-running, user-convenient reactor transient analysis code that has been used to simulate a wide spectrum of thermal-hydraulic transients in both nuclear and nonnuclear systems involving steam-water-noncondensible fluid mixtures. For most of the past decade, however, the Transient Reactor Analysis Code has been the primary code used to simulate transients in which multidimensional hydraulic behavior was anticipated. With the inclusion of the cross-flow junction into RELAP5, however, it has become possible to use RELAP5 to simulate certain components having multidimensional hydraulics, even though RELAP5 is having a one-dimensional code. A novel application of the RELAP5 code to a situation with known three-dimensional hydraulic behavior is presented. The RELAP5 code is currently being used to support restart analyses at the U.S. Department of Energy Savannah River Site (SRS). The computer code and input model were benchmarked against several sets of SRS data to demonstrate their applicability for thermal-hydraulic analysis of SRS production reactors. The benchmarking process provide a significant measure of confidence in the capability of RELAP5 to determine system response in situations where multidimensional hydraulic behavior occurs.

• OSTI ID: 5789169
• Report Number(s): CONF-901101--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 62
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
COMPARATIVE EVALUATIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
COVER GAS
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
FLUIDS
GASES
HEAT EXCHANGERS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
INERT ATMOSPHERE
MECHANICS
NATIONAL ORGANIZATIONS
ONE-DIMENSIONAL CALCULATIONS
OPERATION
OXYGEN COMPOUNDS
PRIMARY COOLANT CIRCUITS
PRODUCTION REACTORS
PUMPS
R CODES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTOR START-UP
REACTORS
SAFETY
SAVANNAH RIVER PLANT
SIMULATION
SPECIAL PRODUCTION REACTORS
START-UP
STEAM
THREE-DIMENSIONAL CALCULATIONS
TRANSIENTS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER