Open AccessTechnical description of the heterogeneous gas core reactor
Author(s) -
N.J. Diaz,
E.T. Dugan,
Ki In Han
Publication year - 1986
Language(s) - English
Resource type - Reports
DOI - 10.2172/6413661
Subject(s) - coolant , nuclear engineering , fissile material , nuclear reactor core , neutron moderator , criticality , homogeneous , neutron , materials science , nuclear physics , neutron temperature , thermodynamics , neutron cross section , physics , engineering
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