Investigation of flow recirculation in a rod bundle during natural-convection flow and power transients. [LMFBR]
Conference
·
OSTI ID:6533093
An experimental investigation conducted at the Pacific Northwest Laboratory studied the flow recirculation phenomenon in a rod bundle during natural-convection flow and power transients. The experimental data were used to validate the recirculation model in the COBRA-WC computer program. The COBRA-WC code was then used to predict the flow and temperature fields in a prototypic Liquid Metal Fast Breeder Reactor (LMFBR) blanket assembly for a worst-case, natural-convection transient. The geometry of the 2 x 6 rod bundle was chosed to facilitate direct velocity measurements by Laser Doppler Anemometry (LDA). The rod bundle power skews ranged from uniform bundle power to 1:0, including 2:1, 3:1, 4:1, and the bundle average Reynolds number ranged from 1400 to 200 for steady flows as well as for a number of 45-sec flow transients. Application of the COBRA-WC code to a prototypic blanket assembly for a worst-case natural-circulation transient shows that, although flow recirculation does occur, the temperature in the recirculating channels is well below the peak assembly temperature.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 6533093
- Report Number(s):
- PNL-SA-10409; CONF-830103-42; ON: DE83007053
- Country of Publication:
- United States
- Language:
- English
Similar Records
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Conference
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Conference
·
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·
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·
OSTI ID:7088966
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210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
CONVECTION
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
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FUEL ASSEMBLIES
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
NATURAL CONVECTION
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
TEST FACILITIES