Open AccessOperational method for demonstrating fuel loading integrity in a reactor having accessible /sup 235/U fuel
Author(s) -
D.R. Ward
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 - 10.2172/5800315
Subject(s) - oak ridge national laboratory , nuclear reactor core , nuclear engineering , core (optical fiber) , control rod , research reactor , nuclear reactor , mox fuel , environmental science , neutron , computer science , engineering , nuclear physics , physics , plutonium , telecommunications
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