TRAC-PF1 analysis of LOFT steam-generator feedwater transient test L9-1. [PWR]
Conference
·
OSTI ID:5732520
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.
- Research Organization:
- Los Alamos National Lab., NM (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 5732520
- Report Number(s):
- LA-UR-83-2780; CONF-830901-14; ON: DE84001303
- Country of Publication:
- United States
- Language:
- English
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Nonbreeding
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Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
COMPUTER CALCULATIONS
ENERGY SYSTEMS
ENERGY TRANSFER
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FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
MECHANICS
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PRESSURE GRADIENTS
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REACTOR SAFETY
REACTORS
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STEAM SYSTEMS
TEMPERATURE GRADIENTS
TRANSIENTS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS