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Evaluation of the thermal-neutron constants for /sup 233/U, /sup 235/U, /sup 239/Pu and /sup 241/Pu
Author(s) -
J. R. Stehn,
M. Divadeenam,
N.E. Holden
Publication year - 1982
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/6848400
Subject(s) - fissile material , uranium 235 , prompt neutron , uranium 238 , nuclide , nuclear physics , fission , isotopes of uranium , plutonium 240 , neutron , plutonium 239 , delayed neutron , neutron temperature , fission product yield , radiochemistry , isotopes of thorium , uranium 233 , physics , uranium , chemistry , thorium , mox fuel

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