Local measurements of flow parameters were performed for vertical upward subcooled boiling flows in an internally heated annulus. The annulus channel consisted of an inner heater rod with a diameter of 19.0 mm and an outer round tube with an inner diameter of 37.5 mm, and the hydraulic equivalent diameter was 18.5 mm. The double-sensor conductivity probe method was used for measuring the local void fraction, interfacial area concentration, bubble Sauter mean diameter and gas velocity, whereas the miniature Pitot tube was used for measuring the local liquid velocity. A total of 32 data sets were acquired consisting of various combinations of heat flux, 88.1–350.9 kW/m2, mass flux, 469.7–1061.4 kg/(m2s) and inlet liquid temperature, 83.8–100.5 °C. Six existing drift-flux models and six existing correlations of the interfacial area concentration were evaluated by the data obtained in the experiment.
Skip Nav Destination
16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4816-7
PROCEEDINGS PAPER
Local Flow Structure of Subcooled Boiling Flow of Water in a Heated Annulus
Tae-Ho Lee,
Tae-Ho Lee
Korea Atomic Energy Research Institute, Daejeon, South Korea
Search for other works by this author on:
Byong-Jo Yun,
Byong-Jo Yun
Korea Atomic Energy Research Institute, Daejeon, South Korea
Search for other works by this author on:
Goon-Cherl Park,
Goon-Cherl Park
Seoul National University, Seoul, South Korea
Search for other works by this author on:
Takashi Hibiki,
Takashi Hibiki
Purdue University, West Lafayette, IN
Search for other works by this author on:
Seong-O Kim
Seong-O Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
Search for other works by this author on:
Tae-Ho Lee
Korea Atomic Energy Research Institute, Daejeon, South Korea
Byong-Jo Yun
Korea Atomic Energy Research Institute, Daejeon, South Korea
Goon-Cherl Park
Seoul National University, Seoul, South Korea
Takashi Hibiki
Purdue University, West Lafayette, IN
Seong-O Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
Paper No:
ICONE16-48170, pp. 233-244; 12 pages
Published Online:
June 24, 2009
Citation
Lee, T, Yun, B, Park, G, Hibiki, T, & Kim, S. "Local Flow Structure of Subcooled Boiling Flow of Water in a Heated Annulus." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 3: Thermal Hydraulics; Instrumentation and Controls. Orlando, Florida, USA. May 11–15, 2008. pp. 233-244. ASME. https://doi.org/10.1115/ICONE16-48170
Download citation file:
18
Views
Related Proceedings Papers
Related Articles
Local Liquid Velocity in Vertical Air-Water Downward Flow
J. Fluids Eng (July,2004)
Vapor Phase Measurements in Subcooled Boiling Flow
J. Heat Transfer (December,2002)
Experimental Investigation of Heat Transfer Coefficient and Correlation Development for Subcooled Flow Boiling of Water–Ethanol Mixture in Conventional Channel
J. Thermal Sci. Eng. Appl (December,2017)
Related Chapters
PVDF/CO 3 O 4 Nanocomposites: Porosity, Crystallinity and Conductivity
International Conference on Advanced Computer Theory and Engineering, 4th (ICACTE 2011)
Experimental Characterization of a Cavitating Orifice
Proceedings of the 10th International Symposium on Cavitation (CAV2018)
Discussion of Parameters to Be Monitored
Consensus on Operating Practices for the Sampling and Monitoring of Feedwater and Boiler Water Chemistry in Modern Industrial Boilers (CRTD-81)