Experiment data report for semiscale Mod-1 test S-28-2 (steam generator tube rupture test). [PWR] [electronic resource].
- Published
- Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1977.
- Physical Description
- Pages: 262 : digital, PDF file
- Additional Creators
- United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- Recorded test data are presented for Test S-28-2 of the Semiscale Mod-1 steam generator tube rupture 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-28-2 was conducted from initial conditions of 15 936 kPa and 558 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 and broken loops to simulate emergency core coolant injection in a PWR. For Test S-28-2, accumulator injection into the intact loop hot leg was provided to simulate simulate the rupture of six steam generator tubes.
- Report Numbers
- E 1.99:tree-nureg-1149
tree-nureg-1149 - Subject(s)
- Other Subject(s)
- Note
- Published through SciTech Connect.
10/01/1977.
"tree-nureg-1149"
Sackett, K.E.; Patton, M.L.
EG and G Idaho, Inc., Idaho Falls (USA) - Funding Information
- EY-76-C-07-1570
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