Laboratory manual for static pressure drop experiments in LMFBR wire wrapped rod bundles
Purpose of this experiment is to determine both interior and edge subchannel axial pressure drops for a range of Reynolds numbers. The subchannel static pressure drop is used to calculate subchannel and bundle average friction factors, which can be used to verify existing friction factor correlations. The correlations for subchannel friction factors are used as input to computer codes which solve the coupled energy, continuity, and momentum equations, and are also used to develop flow split correlations which are needed as input to codes which solve only the energy equation. The bundle average friction factor is used to calculate the overall bundle pressure drop, which determines the required pumping power.
- Research Organization:
- Massachusetts Inst. of Tech., Cambridge (USA). Dept. of Nuclear Engineering
- DOE Contract Number:
- AS02-76ET37240
- OSTI ID:
- 7054213
- Report Number(s):
- DOE/ET/37240-77TR
- Country of Publication:
- United States
- Language:
- English
Similar Records
Laminar, transition, and turbulent parallel flow pressure drop across wire-wrap-spaced rod bundles. [LMFBR]
Subchannel and bundle friction factors and flowsplit parameters for laminar, transition, and turbulent longitudinal flows in wire-wrap spaced hexagonal arrays. [LMFBR]
EVALUATION OF PRESSURE DROP CORRELATIONS FOR THE WIRE-WRAPPED ROD BUNDLES
Journal Article
·
Wed Jan 31 23:00:00 EST 1979
· Nucl. Sci. Eng.; (United States)
·
OSTI ID:6495038
Subchannel and bundle friction factors and flowsplit parameters for laminar, transition, and turbulent longitudinal flows in wire-wrap spaced hexagonal arrays. [LMFBR]
Technical Report
·
Fri Aug 01 00:00:00 EDT 1980
·
OSTI ID:5336242
EVALUATION OF PRESSURE DROP CORRELATIONS FOR THE WIRE-WRAPPED ROD BUNDLES
Conference
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Tue Jun 09 00:00:00 EDT 2020
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OSTI ID:1975123
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
COOLANT LOOPS
COOLING SYSTEMS
CORRELATIONS
DOCUMENT TYPES
EPITHERMAL REACTORS
ERRORS
FAST REACTORS
FBR TYPE REACTORS
FLOW RATE
FRICTION
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MANUALS
PRESSURE DROP
REACTORS
REYNOLDS NUMBER
ROD BUNDLES
210500* -- Power Reactors
Breeding
BREEDER REACTORS
COOLANT LOOPS
COOLING SYSTEMS
CORRELATIONS
DOCUMENT TYPES
EPITHERMAL REACTORS
ERRORS
FAST REACTORS
FBR TYPE REACTORS
FLOW RATE
FRICTION
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MANUALS
PRESSURE DROP
REACTORS
REYNOLDS NUMBER
ROD BUNDLES