Experiment data report for LOFT nonnuclear Test L1-5 (isothermal test with Core 1 installed)

Technical Report · Thu Jun 01 04:00:00 EDT 1978

OSTI ID:6863061

Jacoby, M S

Test data are presented for Test L1-5, which was the fifth of five isothermal nonnuclear tests conducted by the Loss-of-Fluid Test (LOFT) Program. Test L1-5 was the first experiment conducted in LOFT with a nuclear core installed. The nuclear core was held in a shutdown condition. For Test L1-5 the LOFT facility was configured to simulate a loss-of-coolant accident in a large pressurized water reactor resulting from a 200% double-ended offset shear break in a cold leg of the primary coolant system. The initial conditions in the primary coolant system intact loop were: temperature 555 K, pressure 15.55 MPa (absolute), and intact loop flow 176.1 kg/s. During system depressurization into a simulated containment, emergency core cooling water was injected into the primary coolant system cold leg to provide data on the effects of emergency core cooling on system thermal-hydraulic response.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 6863061
• Report Number(s): TREE-NUREG-1215
• Country of Publication: United States
• Language: English

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
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ACCIDENTS
ECCS
ENGINEERED SAFETY SYSTEMS
LOFT REACTOR
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR PROTECTION SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS