ANALYSIS OF COOLANT MIXING IN THE FFTF FUEL BUNDLE.

descriptionPublicationkeyboard_double_arrow_right Report , Other literature type 01 Jan 1968 United States Publisher:Office of Scientific and Technical Information (OSTI)

Authors: Padilla, A. Jr.;

doi: 10.2172/4809836

ANALYSIS OF COOLANT MIXING IN THE FFTF FUEL BUNDLE.

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Abstract

This paper presents some of the coolant mixing studies in the fuel bundle which were carried out during the conceptual stage in the design of the FTR.

Country

United States

Related Organizations

University of North Texas
United States

Keywords

Reactor Core, Fast Test Reactor/Fuel Rod Bundles Of, Temperature Reactor Fuel Elements/Coolant Mixing In Ftr Rod Bundles, Sodium, N38540* --Research & Test Reactors & Critical Assemblies-- Cooling Systems, Fftf, Heat Transfer/Temperature And Coolant Flow Distribution In Ftr Fuel Rod Bundles, Distribution, Heat Transfer, Liquid Metal Coolant, Rods, (T), Reactor Fuel Elements/Coolant Mixing In Ftr Rod Bundles, Numericals, Mixing, Programming, Liquid Flow, Fuel Elements, Heat Transfer And Coolant Mixing In, Research Reactors, Ftr

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