Assessment of CCFL model of RELAP5/MOD3 against simple vertical tubes and rod bundle tests. International Agreement Report

Assessment of CCFL model of RELAP5/MOD3 against simple vertical tubes and rod bundle tests. International Agreement Report [electronic resource]

The CCFL model used in RELAP5/MOD3 version 5m5 has been assessed against simple vertical tubes and bundle tests performed at a facility of Korea Atomic Energy Research Institute. The effect of changes in tube diameter and nodalization of tube section were investigated. The roles of interfacial drags...

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Bibliographic Details
Online Access: Online Access
Corporate Authors: U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (Researcher), United States. Department of Energy. Office of Scientific and Technical Information (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : U.S. Nuclear Regulatory Commission ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1993.
Subjects:
Hydraulics.
Heat Transfer.
Computerized Simulation.
Transients.
Thermal Analysis.
Reactor Safety.
Pwr Type Reactors.
Fluid Flow.
Performance.
Rod Bundles.
R Codes.
Hydraulic Transport.
General And Miscellaneous//mathematics, Computing, And Information Science.
Specific Nuclear Reactors And Associated Plants.

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Call Number: E 1.99:nureg/ia--0100
E 1.99:nureg/ia--0100 Available

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