Experiment data report for Semiscale Mod-1 test S-02-5 (blowdown heat transfer test)
Recorded test data are presented for Test S-02-5 of the Semiscale Mod-1 blowdown heat transfer test series. Test S-02-5 is one of several Semiscale Mod- 1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a water-cooled nuclear reactor system and to provide data for the assessment of the Loss-of-Fluid Test (LOFT) design basis. Test S-02-5 was conducted from an initial cold leg fluid temperature of 544$sup 0$F and an initial pressure of 2,253 psia. A simulated double-ended offset shear cold leg break was used to investigate the system response to a depressurization transient with full core power (1.6 MW). An electrically heated core was used in the pressure vessel to simulate the effects of a nuclear core. System flow was set to achieve the full design core temperature differential of 66$sup 0$F. The flow resistance of the intact loop was based on core area scaling. During system depressurization, core power was reduced from the initial level of 1.6 MW in such a manner as to simulate the surface heat flux response of the LOFT nuclear fuel rods until such time that departure from nucleate boiling occurs. (auth)
- Research Organization:
- SEE CODE- 9502158 Aerojet Nuclear Co., Idaho Falls, Idaho (USA). Idaho National Engineering Lab.
- DOE Contract Number:
- E(10-1)-1375
- NSA Number:
- NSA-33-014064
- OSTI ID:
- 4131840
- Report Number(s):
- ANCR--1235
- Country of Publication:
- United States
- Language:
- English
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PRESSURE GRADIENTS
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TEMPERATURE GRADIENTS
TESTING