Open AccessLOCA simulation in the NRU reactor: materials test-1
Author(s) -
G.E. Russcher,
R.K. Marshall,
G.M. Hesson,
N.J. Wildung,
W. Rausch
Publication year - 1981
Language(s) - English
Resource type - Reports
DOI - 10.2172/5402365
Subject(s) - rod , bundle , nuclear engineering , cladding (metalworking) , thermal hydraulics , pressurized water reactor , loss of coolant accident , coolant , test data , fuel element failure , environmental science , materials science , nuclear reactor core , engineering , mechanics , heat transfer , mechanical engineering , composite material , physics , medicine , alternative medicine , software engineering , pathology