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Kuo-Hsiang Chien, Wei-Keng Lin, Yih-Chean Tsai
Nuclear Technology | Volume 120 | Number 2 | November 1997 | Pages 171-178
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35425
Articles are hosted by Taylor and Francis Online.
The development of a practical and simple on-line void fraction measurement of two-phase flow is of prime interest in applications for nuclear reactor safety research and chemical engineering plants. Experiments were performed at a system pressure of 1 atm. The test sections were made of transparent vertical acrylic pipe with three inner diameters of 1.9, 2, and 2.54 cm. The void fraction was measured by different sizes of side tubes in an air-water two-phase flow; and the void fraction was also compared with the data, which were measured from the liquid holdup between two quick-close valves. The experiment results showed a good agreement for void fractions <0.3, but the error could be large when the flow was in the slug regime.