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Nondestructive fissile isotopic measurement technique for /sup 233/U--/sup 235/U fuels using prompt and delayed fission--neutron counting
Author(s) -
E. J. Allen,
S.R. McNeany
Publication year - 1979
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/6228213
Subject(s) - fissile material , delayed neutron , neutron , uranium 235 , prompt neutron , isotopes of uranium , radiochemistry , fission , uranium 233 , neutron temperature , uranium 238 , calibration , plutonium 239 , uranium , nuclear physics , analytical chemistry (journal) , chemistry , physics , mox fuel , chromatography , quantum mechanics

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