Pump two-phase performance program. Volume IV: comparison of steady-state versus transient test results. Final report

Technical Report · Mon Sep 01 04:00:00 EDT 1980

DOI:https://doi.org/10.2172/6771896· OSTI ID:6771896

Kennedy, W. G.; Jacob, M. C.; Whitehouse, J. C.; Fishburn, J. D.; Kanupka, G. J.

The primary objective of the C-E/EPRI Pump Two-Phase Performance Program was to obtain sufficient steady-state and transient two-phase empirical data to substantiate and ultimately improve the reactor coolant pump analytical model currently used for LOCA analysis. A one-fifth scale pump, which geometrically models a reactor coolant pump, was tested in steady-state runs with single- and two-phase mixtures of water and steam over ranges of operating conditions representative of postulated loss-of-coolant accidents. Transient tests were also run to evaluate the applicability of the steady-state-based calculational models to transient conditions. This project has produced test data which can appropriately be utilized for reactor coolant pump modeling in LOCA analyses. The steady-state test data show general coherence of the test results and overall pump performance trends for a model pump that should be representative of a reactor coolant pump to the extent that scaling laws apply. Both head and torque data correlate well in the form of homologous curves. Two-phase head degradation curves are approximately comparable to head degradation curves obtained in other test programs. Two-phase torque degradation curves have also been developed.

• Research Organization: Combustion Engineering, Inc., Windsor, CT (USA)
• OSTI ID: 6771896
• Report Number(s): EPRI-NP-1556(Vol.4)
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COOLING SYSTEMS
FLUID FLOW
LOSS OF COOLANT
MOCKUP
PERFORMANCE TESTING
PUMPS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
STEADY-STATE CONDITIONS
STRUCTURAL MODELS
TESTING
TRANSIENT OVERPOWER ACCIDENTS
TWO-PHASE FLOW
WATER COOLED REACTORS