Quick-look report on LOFT nuclear experiment L3-2
Loss-of-Coolant Experiment (LOCE) L3-2, the third experiment in the Loss-of-Fluid Test (LOFT) Small Break Series L3 scheduled for performance in the LOFT facility, was successfully completed on February 7, 1980. LOCE L3-2 simulated a single-ended offset shear break of a small (1-in.-dia) pipe connected to the cold leg of a four-loop large pressurized water reactor. After experiment initiation, the primary system depressurization rate stabilized, decreasing system pressure to a point where flow from the high-pressure injection system approximated the break flow. Operator intervention, as planned, was used to reduce system pressure so that the final stage of plant cooldown could be accomplished with the purification system. The reactor system was brought to a cold shutdown condition 6.5 hours after experiment initiation.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 5603750
- Report Number(s):
- EGG-LOFT-5104
- Country of Publication:
- United States
- Language:
- English
Similar Records
Quick-look report on LOFT nonnuclear experiment L3-0
Best estimate prediction for LOFT nuclear experiment L3-2
LOFT monthly progress report for October 1979
Technical Report
·
Sun Jul 01 00:00:00 EDT 1979
·
OSTI ID:6264708
Best estimate prediction for LOFT nuclear experiment L3-2
Technical Report
·
Thu Jan 31 23:00:00 EST 1980
·
OSTI ID:5494761
LOFT monthly progress report for October 1979
Technical Report
·
Wed Oct 31 23:00:00 EST 1979
·
OSTI ID:5715717
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOFT REACTOR
LOSS OF COOLANT
MECHANICS
MOCKUP
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
STRUCTURAL MODELS
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOFT REACTOR
LOSS OF COOLANT
MECHANICS
MOCKUP
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
STRUCTURAL MODELS
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS