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Axial development of subcooled boiling flow in an internally heated annulus
Authors:Rong?Situ,Takashi?Hibiki,Xiaodong?Sun,Ye?Mi,Mamoru?Ishii  author-information"  >  author-information__contact u-icon-before"  >  mailto:ishii@ecn.purdue.edu"   title="  ishii@ecn.purdue.edu"   itemprop="  email"   data-track="  click"   data-track-action="  Email author"   data-track-label="  "  >Email author
Affiliation:(1) School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907-2017, USA;(2) Research Reactor Institute, Kyoto University, Kumatori, 590-0494 Sennan, Osaka, Japan;(3) Present address: En"rsquo"Urga Inc., 1291 Cumberland Avenue, 47906, West Lafayette, IN, USA
Abstract:For the main purpose of database construction in order to develop the interfacial area transport equation, axial developments of local void fraction, interfacial area concentration, bubble Sauter mean diameter, interfacial velocity, and bubble number density were measured in boiling water bubbly flows in a vertical-upward internally heated annulus using a double-sensor conductivity probe. The annulus channel consisted of an inner rod with a diameter of 19.1 mm and an outer round tube with an inner diameter of 38.1 mm, and the hydraulic equivalent diameter was 19.1 mm. A total of 11 data sets were acquired consisting of four inlet liquid velocities, 0.500, 0.664, 0.987 and 1.22 m/s, two heat fluxes, 100 and 150 kW/m2, and two inlet liquid temperatures, 95.0 and 98.0°C. The axial developments of the flow parameters were discussed based on the measured data in detail. In addition to the database construction, the measured data validated recently proposed constitutive equations for the distribution parameter, drift velocity, and bubble Sauter mean diameter, which will improve the accuracy of the drift-flux model in subcooled bubbly flow.
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