Open AccessMSRE DESIGN AND OPERATIONS REPORT. PART III. NUCLEAR ANALYSIS
Author(s) -
P.N. Haubenreich,
J.R. Engel,
B.E. Prince,
H.C. Claiborne
Publication year - 1964
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4114686
Subject(s) - graphite , nuclear graphite , molten salt reactor , neutron flux , neutron moderator , nuclear reactor core , fissile material , materials science , delayed neutron , flux (metallurgy) , nuclear reactor , neutron temperature , analytical chemistry (journal) , nuclear fuel , chemistry , neutron , nuclear physics , molten salt , neutron cross section , nuclear chemistry , physics , composite material , chromatography , metallurgy
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