Axial developments of interfacial area and void concentration profiles in subcooled boiling flow of water |
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| Authors: | Tae-Ho Lee Rong Situ Takashi Hibiki Hyun-Sik Park Mamoru Ishii Michitsugu Mori |
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| Affiliation: | 1. School of Nuclear Engineering, Purdue University, 516 Northwestern Ave., West Lafayette, IN, 47907, USA;1. School of Nuclear Engineering, Purdue University, 516 Northwestern Ave, West Lafayette, IN, 47906, USA;2. Department of Nuclear Science & Technology, Chengdu University of Technology, Sichuan, 610059, PR China;1. Institute of Nuclear and New Energy Technology, Tsinghua University, Key Laboratory of Advanced Reactor Engineering and Safety of the Ministry of Education, Beijing 100084, China;2. School of Nuclear Engineering, Purdue University, 400 Central Dr., West Lafayette, IN 47907, USA |
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| Abstract: | Axial developments of the local void fraction, interfacial area concentration and bubble Sauter mean diameter were measured in subcooled boiling flow of water in a vertical internally heated annulus using the double-sensor conductivity probe technique. Measurements were performed under varying conditions of heat flux, inlet liquid velocity and inlet liquid temperature. A total of 10 data sets were acquired. Based on these measurements with the previous data obtained in the present test loop, the influence of flow condition on the profiles of local two-phase flow parameters was discussed. The measured average void fraction and interfacial area concentration were compared with the predictions by existing correlations for drift-flux parameters and interfacial area concentration. Also, the recently proposed bubble layer thickness model in subcooled boiling was evaluated for the measurement data. |
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