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THERMAL AND TOTAL EPITHERMAL NEUTRON FLUX DISTRIBUTIONS IN THE EXPERIMENTAL GAS COOLED REACTOR
Author(s) -
E. B. Wagner
Publication year - 1960
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4719421
Subject(s) - neutron flux , shield , flux (metallurgy) , graphite , neutron temperature , heat flux , thermal , neutron , materials science , nuclear physics , neutron transport , physics , mechanics , thermodynamics , heat transfer , geology , composite material , petrology , metallurgy

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