EXPERIMENTAL INVESTIGATION OF OPEN LOOP TWO PHASE THERMOSYPHON IN NARROW VERTICAL CHANNEL

Equipment ◽  
2006 ◽  
Author(s):  
J. Aharon ◽  
I. Hochbaum
Keyword(s):  
Experimental Investigation ◽  
Vertical Channel ◽  
Open Loop ◽  
Two Phase

Experimental Investigation of a Two-Phase (Air-Water) Flow in a Pipe with Street Canyon Cavities

2014 ◽  
Vol 8 (6) ◽  
pp. 1149
Author(s):  
Dimitra A. Zoga ◽  
Dimitrios S. Georgakis-Gavrilis ◽  
Dionissios P. Margaris
Keyword(s):  
Experimental Investigation ◽  
Water Flow ◽  
Street Canyon ◽  
Two Phase

A Nondimensional Analysis of Boiling Dry a Vertical Channel with a Uniform Heat Flux

1981 ◽  
Vol 103 (4) ◽  
pp. 667-672 ◽  
Author(s):  
K. H. Sun ◽  
R. B. Duffey ◽  
C. Lin
Keyword(s):  
Heat Flux ◽  
Nuclear Power ◽  
Closed Form Solution ◽  
Vertical Channel ◽  
Form Solution ◽  
Uniform Heat Flux ◽  
Two Phase ◽  
Drift Flux ◽  
Rod Bundle ◽  
Uniform Heat

A thermal-hydraulic model has been developed for describing the phenomenon of hydrodynamically-controlled dryout, or the boil-off phenomenon, in a vertical channel with a spatially-averaged or uniform heat flux. The use of the drift flux correlation for the void fraction profile, along with mass and energy balances for the system, leads to a dimensionless closed-form solution for the predictions of two-phase mixture levels and collapsed liquid levels. The physical significance of the governing dimensionless parameters are discussed. Comparisons with data from single-tube experiments, a 3 × 3 rod bundle experiment, and the Three Mile Island nuclear power plant show good agreement.

Experimental Investigation of Two-Phase Electrolysis Processes in the Alkaline Solution

2013 ◽  
Vol 50 (19) ◽  
pp. 57-62
Author(s):  
Z. Derhoumi ◽  
P. Mandin ◽  
H. Roustan
Keyword(s):  
Experimental Investigation ◽  
Alkaline Solution ◽  
Two Phase

An Experimental Investigation of the Dynamics of a Loosely Supported Tube Array

2017 ◽  
Author(s):  
Amro Elhelaly ◽  
Marwan Hassan ◽  
Atef Mohany ◽  
Soha Moussa
Keyword(s):  
Experimental Investigation ◽  
Impact Force ◽  
Cross Flow ◽  
Open Loop ◽  
Diameter Ratio ◽  
Force Level ◽  
Steam Generators ◽  
Flow Induced Vibration ◽  
System Integrity ◽  
Tube Bundles

The integrity of tube bundles is very important especially when dealing with high-risk applications such as nuclear steam generators. A major issue to system integrity is the flow-induced vibration (FIV). FIV is manifested through several mechanisms including the most severe mechanism; fluidelastic instability (FEI). Tube vibration can be constrained by using tube supports. However, clearances between the tube and their support are required to allow for thermal expansion and for other manufacturing considerations. The clearance between tubes may allow frequent impact and friction between tube and support. This in turn may cause fatigue and wear at support and potential for catastrophic tube failure. This study aims to investigate the dynamics of loosely supported tube array subjected to cross-flow. The work is performed experimentally in an open-loop wind tunnel to address this issue. A loosely-supported single flexible tube in both triangle and square arrays subjected to cross-flow with a pitch-to-diameter ratio of 1.5 and 1.733, respectively were considered. The effect of the flow approach angle, as well as the support clearance on the tube response, are investigated. In addition, the parameters that affect tube wear such as impact force level are presented.

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