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Lumped-parameter fuel rod model for rapid thermal transients [electronic resource]

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Bibliographic Details
Online Access:	Online Access
Corporate Author:	Aerojet Nuclear Company (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Idaho Falls, Idaho : Oak Ridge, Tenn. : Aerojet Nuclear Company ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1975.
Subjects:	Bwr Type Reactors > Loss Of Coolant. Fuel Rods > Temperature Gradients. Pwr Type Reactors > Loss Of Coolant. Loss Of Coolant > Heat Transfer. Hydraulics. Liquid Flow. Mathematical Models. Reactor Safety. N77900* > Reactors > Reactor Safety & Environmental Aspects. N77200 > Reactors > Power Reactors, Non-Breeding, Light-Water Moderated, Non-Boiling Water-Cooled. N77100 > Reactors > Power Reactors, Non-Breeding, Light-Water Moderated, Boiling Water-Cooled. 0900* > Nuclear Reactor Technology > Reactor Safety.

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Call Number:	E 1.99:conf-751101--15
E 1.99:conf-751101--15	Available