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Experiment data report for LOFT anticipated transient without scram Experiment L9-4

Technical Report ·
OSTI ID:6626802
; ;

Selected pertinent and uninterpreted data from the fourth anticipated transient with multiple failures experiment (Experiment L9-4) conducted on September 24, 1982, in the Loss-of-Fluid Test (LOFT) facility are presented. The LOFT facility is a 50-MW(t) pressurized water reactor (PWR) system with instruments that measure and provide data on the system's thermal-hydraulic and nuclear conditions. The operation of the LOFT system is typical of large (approx. 1000 MW(e)), commercial PWR operations. Experiment L9-4 simulated a loss-of-offsite-power anticipated transient without reactor scram. The loss-of-offsite-power accident led to an increase in the primary coolant system temperature and pressure. The experiment safety relief valve opened and was able to limit and control the pressure transient. In addition, subsequent heat generation was dissipated by the auxiliary feedwater flow in the secondary coolant system until the reactor was scrammed at experiment termination.

Research Organization:
Idaho National Engineering Lab., Idaho Falls (USA)
DOE Contract Number:
AC07-76ID01570
OSTI ID:
6626802
Report Number(s):
NUREG/CR-2978; EGG-2227; ON: DE83003372
Country of Publication:
United States
Language:
English

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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ACCIDENTS
ATWS
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
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HYDRAULICS
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PRESSURE GRADIENTS
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REACTOR ACCIDENTS
REACTOR SAFETY
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SAFETY
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TEMPERATURE GRADIENTS
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WATER COOLED REACTORS
WATER MODERATED REACTORS