Dispersed flow film boiling heat transfer data near spacer grids in a rod bundle

Journal Article · Tue Feb 01 04:00:00 EST 1983 · Nucl. Technol.; (United States)

OSTI ID:5313483

Yoder, G L; Morris, D G; Mullins, C B; Ott, L J

A series of steady-state film boiling experiments have been conducted to show the effect of spacer grids on rod bundle heat transfer. Experiments were performed at the Oak Ridge National Laboratory in the Thermal-Hydraulic Test Facility, a pressurized water loop containing a 64-rod bundle, of which 60 rods are electrically heated. The bundle is equipped with detailed thermometry around two grids, which allows grid heat transfer effects to be studied. Rod surface temperature data show a 75 to 150 K temperature difference between measurements upstream and downstream of the grids, while heat transfer coefficients increase across the grids by 20%. Twenty to thirty hydraulic diameters are required for these effects to dissipate.

• Research Organization: Oak Ridge National Laboratory, Bldg. 9204-1, MS-7 P.O. Box Y, Oak Ridge, Tennessee 37830
• OSTI ID: 5313483
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 60:2; ISSN NUTYB
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
BOILING
ELECTRIC HEATING
ENERGY TRANSFER
FILM BOILING
FILMS
FLUID MECHANICS
HEAT TRANSFER
HEATING
HYDRAULICS
MEASURING INSTRUMENTS
MECHANICS
NATIONAL ORGANIZATIONS
ORNL
PHASE TRANSFORMATIONS
ROD BUNDLES
SPACERS
STEADY-STATE CONDITIONS
TEMPERATURE MEASUREMENT
THERMOMETERS
US AEC
US DOE
US ERDA
US ORGANIZATIONS