Open AccessNEUTRON-FLUX MEASUREMENTS IN A FLAT PLATE FUEL ELEMENT
Author(s) -
W.R. Morgan,
J. N. Anno,
J.W. Chastain
Publication year - 1959
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4170970
Subject(s) - neutron flux , neutron temperature , materials science , flux (metallurgy) , research reactor , nuclear reactor core , core (optical fiber) , neutron , thermal , neutron cross section , heat flux , nuclear physics , nuclear engineering , physics , composite material , mechanics , thermodynamics , metallurgy , heat transfer , engineering
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