PLUTONIUM FUEL PROCESSING AND FABRICATION FOR FAST CERAMIC REACTORS
Author(s) -
E.L. Zebroski,
Harvey Alter,
G.D. Collins
Publication year - 1962
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4816118
Subject(s) - plutonium , fabrication , uranium , volume (thermodynamics) , plutonium 240 , nuclear engineering , spent nuclear fuel , mox fuel , materials science , ceramic , waste management , environmental science , chemistry , plutonium 239 , radiochemistry , metallurgy , engineering , nuclear physics , medicine , alternative medicine , physics , pathology , quantum mechanics , fission , neutron
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