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Thermal-hydraulics of the PFB/LOFT lead rod loss-of-coolant experiments. [PWR] [electronic resource]

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Bibliographic Details
Online Access:	Online Access
Corporate Authors:	EG & G Idaho (Researcher), Idaho National Engineering Laboratory (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Idaho Falls, Idaho : Oak Ridge, Tenn. : Idaho National Engineering Laboratory ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1980.
Subjects:	Safety. Hydraulics. Water Moderated Reactors. Water Cooled Reactors. Deformation. Reactors. Reactor Safety. Mechanics. Energy Transfer. Heat Transfer. Fuel Cans. Temperature Gradients. Loss Of Coolant. Reactor Components. Pwr Type Reactors. Blowdown. Fuel Elements. Fuel Element Failure. Fuel Rods. Pressure Gradients. Accidents. Reactor Accidents. Fluid Mechanics. General Studies Of Nuclear Reactors. Specific Nuclear Reactors And Associated Plants.

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Call Number:	E 1.99:conf-801002-1
E 1.99:conf-801002-1	Available