A TRAC-PF1 Analysis of LOFT Steam-Generator Feedwater Transient Test L9-1
The Transient Reactor Analysis Code (TRAC-PF1) calculations were compared to test data from Loss-of-Fluid Test (LOFT) L9-1, which was a loss-of-feedwater transient. This paper includes descriptions of the test and the TRAC input and compares the TRAC-calculated results with the test data. We conclude that the code predicted the experiment well, given the uncertainties in the boundary conditions. The analysis indicates the need to model all the flow paths and heat structures, and to improve the TRAC wall condensation heat-transfer model.
KeywordsSteam Generator Condensation Heat Transfer Decay Heat Pressurizer Spray TRAC Input
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- 1.Douglas L. Reeder, “LOFT System and Test Description (5.5-Ft Nuclear Core 1 LOCES),” Idaho National Engineering Laboratory, NUREG/CR-0247 TREE-1208, July 1978.Google Scholar
- 2.R. J. Beelman, “LOFT Experiment Operating Specification Anticipated Transients With Multiple Failures Test Series L9, Nuclear Test L9-1/L3-3/L8-1A,” Idaho National Engineering Laboratory, EGG-LOFT-5334, April 1981.Google Scholar
- 3.Mary L. McCormick-Barger and Janice M. Divine, “Experiment Data Report for LOFT Anticipated Transient With Multiple Failures Experiment L9-1 and Small Break Experiment L3-3,” Idaho National Engineering Laboratory, NUREG/CR-2119, EGG-2101, June 1981.Google Scholar