Open AccessSimulation of nuclear fuel rods by using process computer-controlled power for indirect electrically heated rods
Author(s) -
S. Malang
Publication year - 1975
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4156872
Subject(s) - rod , control rod , boiler blowdown , nuclear engineering , boiling , scram , materials science , nucleate boiling , heat transfer , coolant , power (physics) , critical heat flux , heat flux , nuclear fuel , mechanics , mechanical engineering , engineering , thermodynamics , physics , medicine , alternative medicine , pathology , inlet
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