Open AccessTHE LONGITUDINAL DISTRIBUTION OF THERMAL NEUTRON FLUX IN CYLINDRICAL FUEL SPECIMENS DURING IRRADIATION
Author(s) -
F.R. Taraba,
S.H. Paine
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 - 10.2172/4217719
Subject(s) - thermal conductivity , heat flux , materials science , thermodynamics , neutron temperature , neutron flux , thermal , constant (computer programming) , flux (metallurgy) , mechanics , thermal conduction , heat transfer , neutron , physics , nuclear physics , metallurgy , computer science , programming language
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