Thermal-hydraulic response of the semiscale Mod-1 system: isothermal test series
Selected experimental thermal-hydraulic data from the recent isothermal blowdown test series performed in the Semiscale Mod-1 geometry are analyzed from an experimental viewpoint with emphasis on explaining differences between the data and expected results. Comparisons are made between the trends measured by the system instrumentation and the trends predicted by analytical tools, including the RELAP4 computer code, to aid in understanding the interactions between phenomena occurring in different parts of the system. The analyses presented are valuable for evaluating the adequacy and improving the predictive capability of analytical models developed to predict the system of a pressurized water reactor during a postulated loss-of-coolant accident (LOCA). 20 references. (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-33-004831
- OSTI ID:
- 4181037
- Report Number(s):
- ANCR--1228
- Country of Publication:
- United States
- Language:
- English
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