Experimental data report for LOFT nonnuclear test L1-3A
Technical Report
·
OSTI ID:7225027
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 542/sup 0/F, pressure at 2242 psig, and loop flow at 2.23 x 10/sup 6/ 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.
- Research Organization:
- SEE CODE- 9502158 EG and G Idaho, Inc., Idaho Falls (USA). Idaho National Engineering Lab.
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 7225027
- Report Number(s):
- TREE-NUREG-1027
- Country of Publication:
- United States
- Language:
- English
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ACCIDENTS
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