Improvements to the RELAP5/MOD3 reflood model and uncertainty quantification of reflood peak clad temperature

Improvements to the RELAP5/MOD3 reflood model and uncertainty quantification of reflood peak clad temperature [electronic resource]

Assessment of the original REAP/N4OD3.1 code against the FLECHT SEASET series of experiments has identified some weaknesses of the reflood model, such as the lack of a quenching temperature model, the shortcoming of the Chen transition boiling model, and the incorrect prediction of droplet size and...

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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: Oak Ridge, Tenn. : Oak Ridge, Tenn. : United States. Dept. of Energy. Office of Scientific and Technical Information ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1996.
Subjects:
Reactor Cores.
Eccs.
Loss Of Coolant.
Thermal Analysis.
Reactor Safety.
Pwr Type Reactors.
Reactor Safety Experiments.
R Codes.
Nuclear Power Reactors And Associated Plants.
Nuclear Reactor Technology.

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Call Number: E 1.99:nureg/ia--0132
E 1.99:nureg/ia--0132 Available

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