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Experiment data report for semiscale Mod-1 test S-06-4 (LOFT counterpart test) [electronic resource].

Published
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1977.
Physical Description
Pages: 265 : digital, PDF file
Additional Creators
United States. Department of Energy. Office of Scientific and Technical Information
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Summary
Recorded test data are presented for Test S-06-4 of the Semiscale Mod-1 LOFT counterpart test series. These tests are among several Semiscale Mod-1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a pressurized water reactor (PWR) system. Test S-06-4 was conducted from initial conditions of 15,653 kPa and 564 K to investigate the response of the Semiscale Mod-1 system to a depressurization and reflood transient following a simulated double-ended offset shear of the broken loop cold leg piping. During the test, cooling water was injected into the cold leg of the intact loop to simulate emergency core coolant injection in a PWR. The heater rods in the electrically heated core were operated at an axial peak power density which was 100 percent of the maximum peak power density (52.5 kW/m).
Report Numbers
E 1.99:tree-nureg-1124
tree-nureg-1124
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
12/01/1977.
"tree-nureg-1124"
Sackett, K. E.; Gillins, R. L.; Coppin, C. E.
SEE CODE- 9502158 EG and G Idaho, Inc., Idaho Falls (USA). Idaho National Engineering Lab.
Funding Information
EY-76-C-07-1570
View MARC record | catkey: 14370246