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ANALYSIS OF COOLANT MIXING IN THE FFTF FUEL BUNDLE. [electronic resource]

Fast Test Reactor/fuel Rod Bundles Of, Heat Transfer And Coolant Mixing In, (t); Reactor Fuel Elements/coolant Mixing In Ftr Rod Bundles, (t); Heat Transfer/temperature And Coolant Flow Distribution In Ftr Fuel Rod Bundles, (t)

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Bibliographic Details
Online Access:	Online Access
Corporate Authors:	Pacific Northwest Laboratory (Researcher), Pacific Northwest National Laboratory (U.S.) (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Richland, Wash. : Oak Ridge, Tenn. : Pacific Northwest National Laboratory (U.S.) ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1968.
Subjects:	Liquid Metal Coolant. Ftr. Numericals. Reactor Core. Fftf. Heat Transfer. Liquid Flow. Mixing. Distribution. Fuel Elements. Rods. Research Reactors. Temperature. Sodium. Programming.

Description
Summary:	Fast Test Reactor/fuel Rod Bundles Of, Heat Transfer And Coolant Mixing In, (t); Reactor Fuel Elements/coolant Mixing In Ftr Rod Bundles, (t); Heat Transfer/temperature And Coolant Flow Distribution In Ftr Fuel Rod Bundles, (t)
Item Description:	Published through the Information Bridge: DOE Scientific and Technical Information. 01/01/1968. "bnwl-sa--1688" " conf-680832--3" Padilla, A. Jr.