Local measurement and numerical calculation on turbulent two-phase flow in a vertical pipe with sudden expansion
- 1. Marine Technical College, Ashiya, Hyogo (Japan)
- 2. Osaka Univ., Osaka (Japan)
Description
Experiment and numerical calculation were carried out for upward, turbulent bubbly two-phase flow in a vertical pipe with an axisymmetric sudden expansion, which is one of the typical multi-dimensional channel geometries. The void fraction, the liquid velocity and turbulent intensity along the flow direction below and the above the sudden expansion point were measured for various turbulent flow conditions by using a point-electrode resistivity probe and a hot-film anemometry probe. They showed quite complicated behaviors depending upon flow rates of gas and liquid phases and bubble size. In particular, the geometry of sudden expansion affected on the bubble behaviors in multi-dimensional two-phase flow, such as the bubble-stagnation, the bubble-deformation, the enhancement and suppression effects due to the two-phase turbulence etc. Through the measurements, fundamental parameters of the two-phase flow were clarified for the sudden expansion channel. Moreover, a three-dimensional one-way bubble tracking simulation of a single bubble behavior in turbulent flow field along the downstream of the sudden expansion was also demonstrated where equation of motion of bubble was solved by assuming appropriate constitutive models and turbulence model. Based on the trajectories of large number of bubbles, the void fraction distribution was predicted in this calculation. It concretely revealed that the lift force and the two-phase turbulence model were the most important parameters in determining the multi-dimensional void fraction distribution and the calculation should be considered by using the measured experimental data. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- NUTHOS-6: Proceedings of the 6th international topical meeting on nuclear reactor thermal hydraulics, operations and safety
- Imprint Pagination
- 3690 p.
- Journal Page Range
- 18 p.
Conference
- Title
- 6. international topical meeting on nuclear reactor thermal hydraulics, operations and safety
- Acronym
- NUTHOS-6
- Dates
- 4-8 Oct 2004
- Place
- Nara (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 36093931
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BUBBLES; ELECTRIC CONDUCTIVITY; ELECTRIC PROBES; EXPANSION; NUMERICAL ANALYSIS; PIPES; TURBULENT FLOW; TWO-PHASE FLOW; VELOCITY; VOID FRACTION
- Descriptors DEC
- ELECTRICAL PROPERTIES; FLUID FLOW; MATHEMATICS; PHYSICAL PROPERTIES; PROBES; TUBES
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name FRIDAY October 8, 2004, Paper ID N6P288.pdf; 34 refs., 15 figs., 1 tab.