Improved guidelines for RELAP4/MOD6 reflood calculations. [PWR]

Improved guidelines for RELAP4/MOD6 reflood calculations. [PWR] [electronic resource]

Computer simulations were performed for an extensive selection of forced- and gravity-feed reflood experiments. This effort was a portion of the assessment procedure for the RELAP4/MOD6 thermal hydraulic computer code. A common set of guidelines, based on recommendations from the code developers, wa...

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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.
Eccs.
Mockup.
Pressure Gradients.
Comparative Evaluations.
Temperature Gradients.
Accidents.
Energy Transfer.
Engineered Safety Systems.
Fluid Mechanics.
Mechanics.
Reactor Accidents.
Reactor Protection Systems.
Reactors.
Safety.
Structural Models.
Mathematical Models.
Water Cooled Reactors.
Reactor Safety.
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--15
E 1.99:conf-800723--15 Available

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