RELAP4/MOD6 analysis of forced- and gravity-feed reflood tests

RELAP4/MOD6 analysis of forced- and gravity-feed reflood tests [electronic resource]

The RELAP4/MOD6 computer code is used for the analysis of the reactor core heat transfer during the reflooding phase of a postulated loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR). The code requires the user to specify input parameters for the reflood heat transfer models. Resu...

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Bibliographic Details
Online Access: Online Access
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:
Loss Of Coolant.
Heat Transfer.
Hydraulics.
Pwr Type Reactors.
Computer Calculations.
Reactor Safety.
Accidents.
Energy Transfer.
Fluid Mechanics.
Reactor Accidents.
Reactors.
Safety.
Mathematical Models.
Water Cooled Reactors.
Mechanics.
Water Moderated Reactors.
General Studies Of Nuclear Reactors.
Specific Nuclear Reactors And Associated Plants.

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Call Number: E 1.99:conf-800723--2
E 1.99:conf-800723--2 Available

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