Measurement of two-phase flow at the core upper plenum interface under simulated reflood conditions. [PWR; BWR]

Conference · Thu Jan 01 00:00:00 EST 1981

OSTI ID:5715966

Thomas, D G; Combs, S K

The Instrument Development Loop (IDL) Program is part of the International 2D/3D Refill and Reflood Experimental and Research Program. The principal experimental facilities in the International Program are the Slab Core Experiment in Japan and the Upper Plenum Test Facility (UPTF) in Germany. Among the objectives of the International Program are: the study of the steam binding effect during reflood for various emergency core cooling combinations; the study of the reflood flow distribution (chimney effect) in a heated core; and the study of the flow hydrodynamics in the core, downcomer, and upper plenum during refill and reflood. A major problem is coupling the results to be obtained at the two major experiments. One approach is to measure the flows at the interface boundary of the two experiments and attempt to match them as closely as possible. Therefore the two major objectives of the IDL Program were to simulate expected flows at the core/upper plenum interface during the reflood phase of a postulated LOCA and to develop instrumentation systems for mass flow measurement at the core/upper plenum interface.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5715966
• Report Number(s): CONF-811042-11; ON: DE85004514
• Resource Relation: Conference: 9. water reactor safety research information meeting, Washington, DC, USA, 26 Oct 1981
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
TEST FACILITIES
TWO-PHASE FLOW
PWR TYPE REACTORS
ECCS
HYDRODYNAMICS
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FLUID FLOW
FLUID MECHANICS
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REACTOR PROTECTION SYSTEMS
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WATER MODERATED REACTORS
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