Heat transfer and hydraulic drag coefficients of a single-row tube bundle in forced convection and subcooled boiling

Journal Article · Sat Apr 01 00:00:00 EST 1989 · Heat Transfer - Soviet Research; (USA)

OSTI ID:6064310

Lokshin, V A; Malkis, V A ^[1]

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1. Dzerzhinskiy Heat Engineering Inst. (SU)

Heat transfer and hydraulics of crossflow of subcooled water over a horizontal single-row tube bundle are analyzed. There exist three zones with different modes of heat transfer. The positions of the boundaries between these zones were determined. These results are used in thermal design of economizers of steam generators of nuclear power plants employing pressurized-water reactors.

• OSTI ID: 6064310
• Journal Information: Heat Transfer - Soviet Research; (USA), Vol. 21:2; ISSN 0440-5749
• Country of Publication: United States
• Language: English

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SUBCOOLED BOILING
CROSSFLOW SYSTEMS
DESIGN
DRAG
FORCED CONVECTION
HEAT TRANSFER
HYDRAULICS
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PHASE TRANSFORMATIONS
POWER PLANTS
REACTORS
THERMAL POWER PLANTS
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420400* - Engineering- Heat Transfer & Fluid Flow
220200 - Nuclear Reactor Technology- Components & Accessories
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Nonbreeding
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