Comparison of numerical results with experimental data for single-phase natural convection in an experimental sodium loop. [LMFBR]
Conference
·
OSTI ID:6043892
A comparison is made between computed results and experimental data for single-phase natural convection in an experimental sodium loop. The tests were conducted in the Thermal-Hydraulic Out-of-Reactor Safety (THORS) Facility, an engineering-scale high temperature sodium facility at the Oak Ridge National Laboratory used for thermal-hydraulic testing of simulated LMFBR subassemblies at normal and off-normal operating conditions. Heat generation in the 19 pin assembly during these tests was typical of decay heat levels. Tests were conducted both with zero initial forced flow and with a small initial forced flow. The bypass line was closed in most tests, but open in one. The computer code used to analyze these tests (LONAC (LOw flow and NAtural Convection)) is an ORNL-developed, fast running, one-dimensional, single-phase finite difference model for simulating forced and free convection transients in the THORS loop.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6043892
- Report Number(s):
- CONF-790808-13
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
AFTER-HEAT
AFTER-HEAT REMOVAL
BREEDER REACTORS
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
CONVECTION
COOLING SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ASSEMBLIES
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NATURAL CONVECTION
PRESSURE DROP
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
REMOVAL
RHR SYSTEMS
TEST FACILITIES
210500* -- Power Reactors
Breeding
AFTER-HEAT
AFTER-HEAT REMOVAL
BREEDER REACTORS
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
CONVECTION
COOLING SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ASSEMBLIES
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NATURAL CONVECTION
PRESSURE DROP
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
REMOVAL
RHR SYSTEMS
TEST FACILITIES