New Interfacial Drag Force Model Including Effect of Bubble Wake, (I) Model Development for Steam-Water Bubbly Flow in Large-Diameter Pipes.

• OKAWA Tomio

  Nuclear Energy Systems Department, Central Research Institute of Electric Power Industry

• YONEDA Kimitoshi

  Nuclear Energy Systems Department, Central Research Institute of Electric Power Industry

• YOSHIOKA Yuzuru

  Research and Development Department, Research and Development Headquarters, The Japan Atomic Power Co.

Bibliographic Information

Other Title

• New Interfacial Drag Force Model Including Effect of Bubble Wake,(1)Model Development for Steam-Water Bubbly Flow in Large-Diameter Pipes
• New Interfacial Drag Force Model Includ
• Model Development for Steam-Water Bubbly Flow in Large-Diameter Pipes

Abstract

Several experimental results show that bubbles can easily be captured in the wake formed by leading bubbles when multiple bubbles are rising in a liquid. It is suggested from this experimental result that the effect of bubble wake should be included in the constitutive relationships representing the interfacial drag force. In the present study, steam-water bubbly flow experiments were performed to develop a new interfacial drag force model including the effect of bubble wake. Since the validity of the existing constitutive equations have been tested mainly for two-phase flow in small-diameter pipes, our study focused on two-phase flow in a large-diameter pipe. Using a one-dimensional two-fluid model, the applicability of the new interfacial drag force model to our experimental conditions was investigated. As a result, it was shown that the present model markedly improves the accuracy of the predicted results. It was therefore demonstrated that the present bubble wake model is effective at least for the conditions which were used for model development. Its applicability to different conditions will be discussed in a subsequent study.

Journal

• Journal of Nuclear Science and Technology

  Journal of Nuclear Science and Technology 35 (12), 895-904, 1998

  Atomic Energy Society of Japan

Keywords

• two-fluid model
• interfacial drag force
• bubble wake
• bubble cluster
• bubble size
• void profile
• distribution parameter
• steam-water two-phase flow
• large-diameter pipes

Details

• CRID: 1390001204095270528
• NII Article ID: 10002080550
• NII Book ID: AA00703720
• DOI: 10.3327/jnst.35.895
• COI: 1:CAS:528:DyaK1MXhtFSnsL8%3D
• ISSN: 18811248
• ISSN: 00223131
• NDL BIB ID: 4629722
• Web Site: https://ndlsearch.ndl.go.jp/books/R000000004-I4629722
• Text Lang: en
• Data Source:
  • JaLC
  • NDL
  • Crossref
  • CiNii Articles
• Abstract License Flag: Disallowed