Subcooled water flow boiling at 1. 66 MPa under uniform high heat flux conditions

Journal Article · Wed Nov 01 04:00:00 EST 1989 · Fusion Technology; (USA)

OSTI ID:6681440

Boyd, Sr, R D ^[1]

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1. Prairie View A and M Univ., TX (USA)

Steady-state subcooled water flow boiling experiments have been carried out in a uniformly heated horizontal circular channel with an exit pressure of 1.66 MPa and with the mass velocity G varying from 4.4 to 32.0 Mg/m{sup 2} {center dot} s. These experiments are related to high heat flux removal in fusion reactor beam dumps and first walls in compact fusion reactors. For the chosen values of L/D and exit pressure, the measured critical heat flux (CHF) values are higher than any previous values for smooth tubes in the literature. An increase in the exit pressure resulted in an increase in the slope of this relationship. However, the local heat transfer coefficient actually decreased as the pressure increased, for the same power level and mass velocity.

• OSTI ID: 6681440
• Journal Information: Fusion Technology; (USA), Journal Name: Fusion Technology; (USA) Vol. 16:3; ISSN 0748-1896; ISSN FUSTE
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700100 -- Fusion Energy-- Plasma Research
700204* -- Fusion Power Plant Technology-- Cooling Systems
BOILING
CLOSED PLASMA DEVICES
COMPACT IGNITION TOKAMAK
COOLING SYSTEMS
CRITICAL HEAT FLUX
ENERGY SYSTEMS
FIRST WALL
HEAT FLUX
HYDROGEN COMPOUNDS
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
STEADY-STATE CONDITIONS
SUBCOOLED BOILING
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
WATER