Open AccessLumped-parameter fuel rod model for rapid thermal transients
Author(s) -
K.R. Perkins,
John D. Ramshaw
Publication year - 1975
Language(s) - English
Resource type - Reports
DOI - 10.2172/4157057
Subject(s) - rod , cladding (metalworking) , loss of coolant accident , thermal , nuclear engineering , coolant , materials science , nuclear fuel , mechanics , heat transfer , heat transfer coefficient , thermodynamics , mechanical engineering , engineering , composite material , physics , medicine , alternative medicine , pathology
The thermal behavior of fuel rods during simulated accident conditions is extremely sensitive to the heat transfer coefficient which is, in turn, very sensitive to the cladding surface temperature and the fluid conditions. The development of a semianalytical, lumped-parameter fuel rod model which is intended to provide accurate calculations, in a minimum amount of computer time, of the thermal response of fuel rods during a simulated loss-of-coolant accident is described. The results show good agreement with calculations from a comprehensive fuel-rod code (FRAP-T) currently in use at Aerojet Nuclear Company. (auth