Abstract
The Transient Reactor Analysis Code (TRAC) is being developed at the Los Alamos Scientific Laboratory as an advanced best-estimate computer program for analyses of postulated accidents in light water reactors. As a part of the TRAC verification effort, a posttest analysis of loss-of-fluid test (LOFT) non-nuclear test L1-4 has been conducted. The results of this analysis show that TRAC accurately predicts the thermal-hydraulic response of the entire LOFT system, including the delayed effects from emergency core coolant injection into the cold leg.
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