Simulation of three-dimensional hydrodynamic components with a one-dimensional transient analysis code
Conference
·
OSTI ID:6434542
Significant multidimensional pressure gradients occur in the water plenum region of the reactors at the Savannah River Site (SRS). A multidimensional RELAP5 input model of the L-Reactor was developed and benchmarked against SRS data. Although RELAP5 is a one-dimensional code, its cross-flow junction allows a multidimensional analysis capability. RELAP5 and the model of L-Reactor calculated water plenum pressures that were in good agreement with measured values for tests with symmetric and asymmetric flow patterns within the plenum. The results indicate that a one-dimensional code such as RELAP5, in conjunction with a carefully designed input model, can be used to predict hydraulic response even when large multidimensional effects are present. 6 refs., 6 figs.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6434542
- Report Number(s):
- EGG-M-90343; CONF-901154--1; ON: DE91001816
- Country of Publication:
- United States
- Language:
- English
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Simulation of three-dimensional hydrodynamic components with a one-dimensional transient analysis code
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A comparison of RELAP5 and TRAC LOCA (loss-of-coolant accident) calculations for the K-14. 1 charge at SRS (Savannah River Site)
Conference
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Sun Dec 31 23:00:00 EST 1989
· Transactions of the American Nuclear Society; (USA)
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OSTI ID:5789169
Simulation of three-dimensional hydrodynamic components with a one-dimensional transient analysis code
Conference
·
Sun Dec 31 23:00:00 EST 1989
·
OSTI ID:6892144
A comparison of RELAP5 and TRAC LOCA (loss-of-coolant accident) calculations for the K-14. 1 charge at SRS (Savannah River Site)
Technical Report
·
Tue Aug 01 00:00:00 EDT 1989
·
OSTI ID:7175249
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
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
BENCHMARKS
COMPUTER CODES
ENERGY TRANSFER
FLOW MODELS
FLUID MECHANICS
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
HYDRAULICS
HYDRODYNAMICS
L REACTOR
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
NATIONAL ORGANIZATIONS
PRESSURE GRADIENTS
PRODUCTION REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
SAVANNAH RIVER PLANT
SPECIAL PRODUCTION REACTORS
T CODES
TRANSIENTS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700* -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900 -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
BENCHMARKS
COMPUTER CODES
ENERGY TRANSFER
FLOW MODELS
FLUID MECHANICS
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
HYDRAULICS
HYDRODYNAMICS
L REACTOR
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
NATIONAL ORGANIZATIONS
PRESSURE GRADIENTS
PRODUCTION REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
SAVANNAH RIVER PLANT
SPECIAL PRODUCTION REACTORS
T CODES
TRANSIENTS
US AEC
US DOE
US ERDA
US ORGANIZATIONS