Post Critical Heat Flux (CHF) heat transfer and quenching [PWR]

Post Critical Heat Flux (CHF) heat transfer and quenching [PWR] [electronic resource]

This paper describes quantitatively new mechanisms in the post-CHF regime which provide understanding and predictive capability for several current two-phase forced convective heat transfer problems. These mechanisms are important in predicting rod temperature turnaround and quenching during the ref...

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Bibliographic Details
Online Access: Online Access (via OSTI)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. Department of Energy. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1980.
Subjects:
Critical Heat Flux.
Pwr Type Reactors.
Reactor Accidents.
Film Boiling.
Heat Transfer.
Hydraulics.
Reactor Safety.
Accidents.
Boiling.
Fluid Mechanics.
Heat Flux.
Mechanics.
Phase Transformations.
Reactors.
Safety.
Water Cooled Reactors.
Energy Transfer.
Water Moderated Reactors.
General Studies Of Nuclear Reactors.
Specific Nuclear Reactors And Associated Plants.

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Call Number: E 1.99:conf-801102--4
E 1.99:conf-801102--4 Available

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