EQUATIONS FOR BILATERAL HEAT TRANSFER TO FLUIDS FLOWING IN CONCENTRIC ANNULI
Technical Report
·
OSTI ID:4733736
Theoretical equations were derived for calculating heat transfur coefficients for fluids flowing through concentric annuli for the following two cases: (A) constant and equal heat tluxes from both walls, and (B) constant, but unequal, heat fluxes from the walls, with equal wall temperatures at a given axial position along annular channel. In the derivations, the conditions of fully-established flow, and independence of physical properties with temperature variation across the flow channel, were assumed. The only geometrical parameter in this general case is the radius ratio r/sub 2//r/sub 1/, and in the study it was varied from 1.0 to 10.0. (auth)
- Research Organization:
- Brookhaven National Lab., Upton, N.Y.
- DOE Contract Number:
- AT(30-2)-GEN-16
- NSA Number:
- NSA-17-008321
- OSTI ID:
- 4733736
- Report Number(s):
- BNL-6173
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-63
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ENGINEERING AND EQUIPMENT
ALPHA DECAY
AMERICIUM 241
ANNULAR SPACE
BURNUP
CONFERENCE
CONFIGURATION
COOLANT LOOPS
ECONOMICS
FABRICATION
FLUID FLOW
FUEL ELEMENTS
GAS COOLANT
HALF-LIFE
HEAT TRANSFER
HEATING
HIGH TEMPERATURE
MEASURED VALUES
NEUTRON FLUX
PEBBLE BED
PELLETS
PLANNING
POWER PLANTS
REACTOR CORE
REACTOR FUELING
REPROCESSING
SPACERS
STANDARDS
SURFACES
TEMPERATURE
THERMODYNAMICS
TUBES
ALPHA DECAY
AMERICIUM 241
ANNULAR SPACE
BURNUP
CONFERENCE
CONFIGURATION
COOLANT LOOPS
ECONOMICS
FABRICATION
FLUID FLOW
FUEL ELEMENTS
GAS COOLANT
HALF-LIFE
HEAT TRANSFER
HEATING
HIGH TEMPERATURE
MEASURED VALUES
NEUTRON FLUX
PEBBLE BED
PELLETS
PLANNING
POWER PLANTS
REACTOR CORE
REACTOR FUELING
REPROCESSING
SPACERS
STANDARDS
SURFACES
TEMPERATURE
THERMODYNAMICS
TUBES