Open AccessPRELIMINARY REPORT ON THE RESULTS OF THE OAK RIDGE RESEARCH REACTOR HYDRAULIC TEST
Author(s) -
F.T. Binford
Publication year - 1958
Language(s) - English
Resource type - Reports
DOI - 10.2172/4309490
Subject(s) - oak ridge national laboratory , coolant , thermal hydraulics , heat flux , nuclear engineering , mass flux , flux (metallurgy) , materials science , ridge , thermal , range (aeronautics) , research reactor , inlet , thermodynamics , environmental science , mechanics , mechanical engineering , heat transfer , nuclear physics , composite material , engineering , physics , metallurgy , geology , neutron , paleontology