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Two-Phase Flow Models and their Limitations

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Advances in Two-Phase Flow and Heat Transfer

Part of the book series: NATO ASI Series ((NSSE,volume 63))

Abstract

An accurate prediction of transient two-phase flow is essential to safety analyses of nuclear reactors under accident conditions. The fluid flow and heat transfer encountered are often extremely complex due to the reactor geometry and occurrence of transient two-phase flow. Recently considerable progresses in understanding and predicting these phenomena have been made by a combination of rigorous model development, advanced computational techniques, and a number of small and large scale supporting experiments. In view of their essential importance, the foundation of various two-phase flow models and their limitations are discussed in this paper.

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Author information

Authors and Affiliations

  1. Reactor Analysis and Safety Division, Argonne National Laboratory, Argonne, Illinois, USA

    M. Ishii & G. Kocamustafaogullari

  2. University of Wisconsin at Milwaukee, Milwaukee, Wisconsin, USA

    M. Ishii & G. Kocamustafaogullari

Authors
  1. M. Ishii
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  2. G. Kocamustafaogullari
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Editor information

Editors and Affiliations

  1. University of Miami, Coral Gables, Florida, USA

    S. Kakaç

  2. Argonne National Laboratory, Argonne, Illinois, USA

    M. Ishii

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© 1983 Martinus Nijhoff Publishers, The Hague

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Ishii, M., Kocamustafaogullari, G. (1983). Two-Phase Flow Models and their Limitations. In: Kakaç, S., Ishii, M. (eds) Advances in Two-Phase Flow and Heat Transfer. NATO ASI Series, vol 63. Springer, Dordrecht. https://doi.org/10.1007/978-94-009-6845-5_1

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  • DOI: https://doi.org/10.1007/978-94-009-6845-5_1

  • Publisher Name: Springer, Dordrecht

  • Print ISBN: 978-94-009-6847-9

  • Online ISBN: 978-94-009-6845-5

  • eBook Packages: Springer Book Archive

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