Steady-state heat transfer in an inverted U-tube steam generator
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-
- Resource Relation:
- Conference: American Society of Mechanical Engineers winter meeting, Anaheim, CA, USA, 7 Dec 1986; Other Information: Technical Paper 86-WA/NE-6
- Country of Publication:
- United States
- Language:
- English
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Steady-state heat transfer in an inverted U-tube steam generator
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