Open AccessExperiment requirements to determine and relate fuel damage limits to core-wide conditions in pressurized water reactors
Author(s) -
D.D. Croucher,
R.J. Loyd
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 - 10.2172/6021687
Subject(s) - cladding (metalworking) , thermal hydraulics , nuclear engineering , pressurized water reactor , boiling water reactor , limit (mathematics) , rod , core (optical fiber) , thermal , nuclear reactor core , boiling , control rod , environmental science , materials science , engineering , mechanical engineering , heat transfer , mechanics , thermodynamics , composite material , physics , medicine , mathematical analysis , mathematics , alternative medicine , pathology
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