Experimental study of diversion cross-flow caused by subchannel blockages: Volume 2, Two-phase flow: Final report

Technical Report · Mon Feb 01 00:00:00 EST 1988

OSTI ID:5578978

Tapucu, A; Teyssedou, A; Geckinli, M; Troche, N

Experiments were performed to study the effects of a blockage in one subchannel of a two-subchannel test section model of a reactor fuel bundle. Smooth- and sharp-edged blockages were used. The test fluid consisted of two-phase air-water mixtures. The data were compared with calculated results obtained from the COBRA III-C code. Good agreement was obtained from smooth blockages of less than 60% and for sharp blockages of less than 30%. 35 refs., 206 figs., 17 tabs.

• Research Organization: Ecole Polytechnique, Montreal, Quebec (Canada)
• OSTI ID: 5578978
• Report Number(s): EPRI-NP-3459-Vol.2; ON: TI88920197
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
FUEL ELEMENTS
FLOW BLOCKAGE
HEAT TRANSFER
HYDRAULICS
C CODES
LOSS OF COOLANT
NUCLEAR POWER PLANTS
EXPERIMENTAL DATA
FLOW MODELS
PROGRESS REPORT
THEORETICAL DATA
TWO-PHASE FLOW
ACCIDENTS
COMPUTER CODES
DATA
DOCUMENT TYPES
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
INFORMATION
MATHEMATICAL MODELS
MECHANICS
NUCLEAR FACILITIES
NUMERICAL DATA
POWER PLANTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety