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Neutron flux computational model of the Oak Ridge research reactor
Author(s) -
E.J. Allen,
H.T. Kerr
Publication year - 1975
Language(s) - English
Resource type - Reports
DOI - 10.2172/4214347
Subject(s) - oak ridge national laboratory , ridge , nuclear engineering , research reactor , flux (metallurgy) , neutron flux , nuclear physics , environmental science , neutron , materials science , physics , geology , engineering , metallurgy , paleontology

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