Intact loop pump performance during the Semiscale Mod-1 isothermal test series
An analysis was performed on the Semiscale Mod-1 intact loop pump data taken during the Semiscale Mod-1 isothermal test series. The pump was shown to directly affect intact loop and vessel flow rates during the early portion of the simulated loss-of-coolant accidents (LOCAs). Comparison of pump performance data taken during the Semiscale Mod-1 isothermal tests with data obtained during previous steady state and transient tests indicated that the pump head degraded more rapidly during the Semiscale Mod-1 tests. Calculations using the pump model contained in the RELAP4 computer program are compared with these pump performance data. Areas of operation for the Semiscale Mod-1 pump are defined for the transient two-phase steam-water flows that occurred during several isothermal blowdown tests, and suggested refinement in the two-phase characteristics of the Semiscale Mod-1 pump model is offered. 13 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-33-006802
- OSTI ID:
- 4158858
- Report Number(s):
- ANCR--1240
- Country of Publication:
- United States
- Language:
- English
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