Measurement of Interfacial Area Concentration and Void Fraction with Double-sensor Probe in a Vertical Upward Annular Pipe

• Main Authors: Hsu, Chung-Yen, 徐仲彥
• Other Authors: Pei, Bau-Shei
• Format: Others
• Language: zh-TW
• Published: 2017
• Online Access: http://ndltd.ncl.edu.tw/handle/wgar7z

碩士 === 國立清華大學 === 工程與系統科學系 === 105 === Bubbly flow phenomenon is the most common flow pattern in nuclear plant system. In this paper, the experiment was designed to observe the fluid phenomenon surrounding nuclear rod bundle, and developed the measurement method in an annulus pipe measured by double sensor probe. In recent years, double sensor probe is one of the measuring techniques for the bubbly flow. It can measure local void fraction and bubble velocity. After mathematical statistical calculation, interfacial area concentration and sauter mean diameter were obtained. A total of 9 data consisted of four superficial liquid velocities, 0.31, 0.41, 0.51, and 0.61 m/s, and four superficial liquid velocities, 0.02, 0.03, 0.05, and 0.13 m/s. The obtained data will be compared and used to develop to the two phase model for Computational Fluid Dynamics