Experiment data report for LOFT nonnuclear Test L1-5 (isothermal test with Core 1 installed)
Description
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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A13/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 298 p.
- Report number
- TREE-NUREG--1215
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9418028
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ECCS; LOFT REACTOR; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR CORES; SIMULATION
- Descriptors DEC
- ACCIDENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS