Comparison of measured and calculated LWR fuel behavior during a hypothetical reactivity initiated accident

Comparison of measured and calculated LWR fuel behavior during a hypothetical reactivity initiated accident [electronic resource]

Comparisons of measured and calculated LWR fuel rod responses during a reactivity initiated accident test are presented. The results indicate that the computer code, FRAP-T5, adequately calculates the fuel rod behavior up to the time at which the gap closes and provides a good thermal solution up to...

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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:
Bwr Type Reactors.
Transients.
Fuel Rods.
Deformation.
Meltdown.
Pwr Type Reactors.
Fuel Element Failure.
Mathematical Models.
Reactivity Insertions.
Reactor Accidents.
Reactor Safety.
Accidents.
Fuel Elements.
Reactor Components.
Reactors.
Safety.
Water Cooled Reactors.
Reactivity.
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--7
E 1.99:conf-800723--7 Available

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