Steady-state heat transfer in an inverted U-tube steam generator

Conference · Thu Jan 01 04:00:00 EST 1987

OSTI ID:5689704

Boucher, T J

Experimental results are presented involving U-tube steam generator tube bundle local heat transfer and fluid conditions during stead-state, full-power operations performed at high temperatures and pressures with conditions typical of a pressurized water reactor (15.0 MPa primary pressure, 600 K steam generator inlet plenum fluid temperatures, 6.2 MPa secondary pressure). The Semiscale (MOD-2C facility represents the state-of-the-art in measurement of tube local heat transfer data and average tube bundle secondary fluid density at several elevations, which allows an estimate of the axial heat transfer and void distributions during steady-state and transient operations. The method of heat transfer data reduction is presented and the heat flux, secondary convective heat transfer coefficient, and void fraction distributions are quantified for steady-state, full-power operations.

• OSTI ID: 5689704
• Report Number(s): CONF-861211-
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
AXIAL SYMMETRY
BOILERS
CONVECTION
ENERGY TRANSFER
HEAT EXCHANGERS
HEAT FLUX
HEAT TRANSFER
HIGH TEMPERATURE
MASS TRANSFER
MEDIUM PRESSURE
OPERATION
PWR TYPE REACTORS
REACTOR OPERATION
REACTORS
STEADY-STATE CONDITIONS
STEAM GENERATORS
SYMMETRY
TEMPERATURE DISTRIBUTION
THERMODYNAMICS
VAPOR GENERATORS
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS