Measurement of two-phase flow at the core upper plenum interface under simulated reflood conditions

Conference · Mon Dec 31 23:00:00 EST 1979

OSTI ID:6987060

Thomas, D G; Combs, S K; Bagwell, M E

Objectives of the Instrument Development Loop program were to simulate flows at the core/upper plenum interface during the reflood phase of a LOCA and to develop instruments for measuring mass-flows at this interface. A tie plate drag body was developed and tested successfully, and the data obtained were shown to be equivalent to pressure drops. The tie-plate drag body gave useful measurements in pure downflow, and the drag/turbine combination correlates with mass flow for high upflow. (DLC)

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6987060
• Report Number(s): CONF-801053-3
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CORE FLOODING SYSTEMS
DRAG
ECCS
ENGINEERED SAFETY SYSTEMS
FLOWMETERS
FLUID FLOW
INTERFACES
LOSS OF COOLANT
MACHINERY
MEASURING INSTRUMENTS
METERS
PRESSURE DROP
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
TURBINES
TURBOMACHINERY
TWO-PHASE FLOW
WATER COOLED REACTORS