Experimental data report for LOFT nonnuclear test L1-3A
Description
Test L1-3A was the third in a series of five nonnuclear isothermal blowdown tests conducted by the Loss of Fluid Test (LOFT) Program. For this test the LOFT Facility was configured to simulate a loss-of-coolant accident in a large pressurized water reactor resulting from a 200 percent double-ended shear break in a cold leg of the primary coolant system. A hydraulic core simulator assembly was installed in place of the nuclear core. The initial conditions in the primary coolant system intact loop were: temperature at 5420F, pressure at 2242 psig, and loop flow at 2.23 x 106 lbm/hr. During system depressurization, emergency core cooling water was injected into the lower plenum of the reactor vessel to provide data on the effects of emergency core cooling on system response. The experiment was successful in that the objectives outlined in the experiment operating specification for this test were accomplished
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS. $9.00.
Files
Additional details
Publishing Information
- Imprint Pagination
- 267 p.
- Report number
- TREE-NUREG--1027
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8324873
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DEPRESSURIZATION; ECCS; LOFT REACTOR; LOSS OF COOLANT; MOCKUP; PERFORMANCE; PWR TYPE REACTORS; SIMULATION
- Descriptors DEC
- ACCIDENTS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; STRUCTURAL MODELS; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS