Bubble behaviour and mean diameter in subcooled flow boiling [electronic resource].
- Published
- Rockville, Md. : U.S. Nuclear Regulatory Commission, 1995.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy - Physical Description
- pages 3,175-3,196 : digital, PDF file
- Additional Creators
- U.S. Nuclear Regulatory Commission and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- Bubble behaviour and mean bubble diameter in subcooled upward flow boiling in a vertical annular channel were investigated under low pressure and mass flux conditions. A high speed video system was used to visualize the subcooled flow boiling phenomenon. The high speed photographic results indicated that, contrary to the common understanding, bubbles tend to detach from the heating surface upstream of the net vapour generation point. Digital image processing technique was used to measure the mean bubble diameter along the subcooled flow boiling region. Data on the axial area-averaged void fraction distributions were also obtained using a single beam gamma densitometer. Effects of the liquid subcooling, applied heat flux and mass flux on the mean bubble size were investigated. A correlation for the mean bubble diameter as a function of the local subcooling, heat flux and mass flux was obtained.
- Report Numbers
- E 1.99:nureg/cp--0142-vol.4
E 1.99: conf-950904--vol.4
conf-950904--vol.4
nureg/cp--0142-vol.4 - Subject(s)
- Note
- Published through SciTech Connect.
09/01/1995.
"nureg/cp--0142-vol.4"
" conf-950904--vol.4"
"TI95017080"
7. international topical meeting on nuclear reactor thermal-hydraulics (Nureth-7), Saratoga Springs, NY (United States), 10-15 Sep 1995.
Zeitoun, O.; Shoukri, M. [McMaster Univ., Hamilton, Ontario (Canada)].
View MARC record | catkey: 23769959