Open AccessMaterials Test-2 LOCA Simulation in the NRU Reactor
Author(s) -
J.O. Barner,
G.M. Hesson,
I. L. King,
R.K. Marshall,
L.J. Parchen,
J.P. Pilger,
W. Rausch,
G.E. Russcher,
B.J. Webb,
N.J. Wildung,
Clark L. Wilson,
M. D. Wismer,
C.L. Mohr
Publication year - 1982
Language(s) - English
Resource type - Reports
DOI - 10.2172/1084042
Subject(s) - rod , nuclear engineering , bundle , cladding (metalworking) , pressurized water reactor , loss of coolant accident , light water reactor , fuel element failure , environmental science , coolant , materials science , nuclear reactor core , nuclear physics , engineering , physics , composite material , medicine , alternative medicine , pathology
A simulated loss-of-coolant accident was performed with a full-length test bundle of pressurized water reactor fuel rods. This third experiment of the program produced fuel cladding temperatures exceeding 1033 K (1400°F) for 155 s and resulted in eight ruptured fuel rods. Experiment data and initial results are presented in the form of photographs and graphical summaries