Flow characteristics of bubbly countercurrent flow

Conference · Sat Jun 01 04:00:00 EDT 1996

OSTI ID:234272

Aritomi, Masanori; Zhou, Shirong ^[1]; Nakajima, Makoto ^[2]; Mizoguchi, Junji ^[3]; Takeda, Yasushi ^[4]; Mori, Michitugu ^[5]; Yoshioka, Yuzuru ^[6]

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1. Tokyo Inst. of Tech. (Japan)
2. Mitsubishi Heavy Industry Co., Kobe (Japan)
3. Shibaura Inst. of Tech., Omiya (Japan)
4. Paul Scherrer Inst., Villigen (Switzerland)
5. Tokyo Electric Power Co. (Japan)
6. Japan Atomic Power Co., Tokyo (Japan)

Many concepts have been proposed for future LWRs in which passive and simplified safety functions are actively introduced with the aim of enhancing the reliability of their safety features, maintainability and so on. However, since passive safety features are functioned by the law of nature, the driving force induced by them is much smaller than that induced by active ones, e.g. a gravity-driven coolant injection system. Consequently, it is necessary with regard to passive safety features to be able to simulate multi-dimensional dynamics even for the two-phase flow which can be regarded as one dimensional flow for active ones. The authors have developed a measurement system which is composed of an ultrasonic velocity profile monitor and a video data processing unit in order to clarify its multi-dimensional flow characteristics in bubbly flow and to offer a data base to validate numerical codes for multi-dimensional two-phase. In this paper, the measurement system is applied for bubbly countercurrent flows in a vertical rectangular channel. Both bubble and water velocity profiles and void fraction profiles in the channel were investigated statistically. Next, the distribution parameter and drift flux used in the drift flux model were obtained. Finally, the profile of two-phase multiplier of turbulent intensity in the channel was discussed.

• OSTI ID: 234272
• Report Number(s): CONF-960306--; ISBN 0-7918-1226-X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
COMPUTER CODES
ENGINEERED SAFETY SYSTEMS
MEASURING INSTRUMENTS
MEASURING METHODS
TWO-PHASE FLOW
VALIDATION
WATER COOLED REACTORS