Open AccessTHE LARGE COMPONENT TEST LOOP-DESCRIPTION AND OPERATING CAPABILITIES
Author(s) -
R.W. Atz
Publication year - 1963
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4001100
Subject(s) - loop (graph theory) , nuclear engineering , head (geology) , rod , flow (mathematics) , component (thermodynamics) , sodium cooled fast reactor , thermal , volumetric flow rate , mechanics , materials science , control rod , mechanical engineering , environmental science , engineering , physics , thermodynamics , geology , mathematics , medicine , alternative medicine , pathology , combinatorics , geomorphology
The Large Component Test Loop is a facility for ASCR providing experimental capacity for subjecting large components, such as moderator assemblies and control rods, to thermal gradients and transients at varying rates of sodium flow to simulate reactor operating conditions. Two separate loops are used for heating and cooling the sodium as the testing is performed. The 3-inch pump loop, modified to operate at 1200 deg F, was operated at a flow of 130 gpm and a head of 25 feet. The 6-inch pump loop, limited to 1000 deg F operation by materials of construction, was operated at a flow of 2000 gpm and head of 65 feet. The rest of the facility has operated satisfactorily at 1200 deg F. (auth
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