Semiscale loss-of-power test results. [PWR]
Technical Report
·
OSTI ID:5691875
The Semiscale Program and Test facility are located at the Idaho National Engineering Laboratory, and operated by EG and G Idaho, Incorporated for the US Department of Energy. The system is a small-scale model of the primary coolant system of a pressurized water reactor (PWR) nuclear generating plant. It incorporates the major components of a PWR and is capable of attaining typical operating pressures and temperatures. An experimental program designed to provide data from loss-of-power transients was conducted in Semiscale in FY-83 in support of programs sponsored by the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. This Semiscale program provides information relative to resolution of the station blackout safety issue through validation of thermal-hydraulic computer codes used in accident sequence analyses. Description of the experimental objectives, scenarios, and results is presented.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5691875
- Report Number(s):
- EGG-M-22283; CONF-8310143-48; ON: DE84002211
- Country of Publication:
- United States
- Language:
- English
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Fri Dec 31 23:00:00 EST 1982
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Experimental operating specification tests S-08-1 through S-08-08. Semiscale Mod-3 UHI test series. [PWR]
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Summary of the Semiscale Program, 1965-1986
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