TRAC-PF1 analysis of loss-of-fluid test L6-7/L9-2
The Los Alamos National Laboratory is developing the Transient Reactor Analysis Code (TRAC-PF1) to provide the capability for advanced best-estimate predictions of postulated accidents in pressurized-water reactors (PWRs) and for many thermal-hydraulic experimental facilities. As part of an independent assessment of TRAC-PF1, Loss-of-Fluid Test (LOFT) L6-7/L9-2 is analyzed and compared to the calculated results. Test L6-7 simulated a cooldown transient similar to the Arkansas Nuclear One Unit-2 turbine-trip transient. During the L9-2 phase of the test, the primary-coolant pumps were tripped and natural circulation cooled the core while the plant cooldown continued. The TRAC results matched the test data well during the L6-7 portion of the transient (0.0-324 s). However, during the L9-2 portion the calculated natural-circulation flow rate in the intact loop was much higher than the measured rate.
- Research Organization:
- Los Alamos National Lab., NM (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 7030180
- Report Number(s):
- LA-UR-83-3658; CONF-840813-1; ON: DE84004415
- Country of Publication:
- United States
- Language:
- English
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ACCIDENTS
COMPUTER CALCULATIONS
CONVECTION
DATA
ENERGY TRANSFER
EXPERIMENTAL DATA
FLOW RATE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INFORMATION
LOSS OF FLOW
MECHANICS
NATURAL CONVECTION
NUMERICAL DATA
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
THEORETICAL DATA
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS