TWO-PHASE FLOW AND HEAT TRANSFER IN MULTIROD GEOMETRIES. AIR--WATER FLOW STRUCTURE DATA FOR A ROUND TUBE, CONCENTRIC AND ECCENTRIC ANNULUS, AND NINE-ROD BUNDLE.

Technical Report · Wed Jan 01 00:00:00 EST 1969

DOI:https://doi.org/10.2172/4786101· OSTI ID:4786101

Schraub, F. A.; Simpson, R. L.; Janssen, E.

• Research Organization: General Electric Co., San Jose, Calif. Atomic Power Equipment Dept.
• DOE Contract Number: AT(04-3)-189
• NSA Number: NSA-23-033323
• OSTI ID: 4786101
• Report Number(s): GEAP-5739
• Resource Relation: Other Information: UNCL. Orig. Receipt Date: 31-DEC-69
• Country of Publication: United States
• Language: English

Related Subjects

N24300* -Engineering-Heat Transfer & Fluid Flow
AIR
ANNULAR SPACE
CONFIGURATION
COOLANTS
FILMS
FLUID FLOW
FUEL ELEMENTS
HEAT TRANSFER
LABORATORY EQUIPMENT
LIQUIDS
OPENINGS
OPERATION
POROSITY
PRESSURE
REACTORS
RINGS
SURFACES
TEMPERATURE
THICKNESS
TUBES
TWO- PHASE FLOW
VALVES
VAPORS
VELOCITY
VOID FRACTION
WATER
FLUID FLOW/pressure drop in vertical two-phase, effects of system pressure, pressure fluctuations, and temperature on
WATER/air- H$sub 2$O, flow in round tubes, concentric and eccentric annulus, and nine-rod bundle
FLUID FLOW/void fraction in vertical two-phase
use of quick-closing valves for measurement of
REACTOR FUEL ELEMENTS/fluid flow in nine-rod bundles of
analysis of two-phase
VOID FRACTION/measurement of average
in two-phase fluid flow
use of quick-closing valves for
PRESSURE DROP/measurements for two- phase flow in multirod geometries
HEAT TRANSFER/analysis in annular-dispersed flow regime
COMPUTER PROGRAMS/WADR, for calculation of pressure drop, void fraction, and flow conditions for two-phase flow, FORTRAN IV
FLUID FLOW/ measurement of two-phase
in multirod geometries
equipment and methods for
AIR/ air-H$sub 2$O, flow in round tubes, concentric and eccentric annulus, and nine- rod bundle