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CHF and Post-CHF Heat Transfer : An Assessment of Prediction Methods and Recommendations for Reactor Safety Codes

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Advances in Two-Phase Flow and Heat Transfer

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

Abstract

A number of excellent reviews of the CHF and post-CHF heat transfer literature have previously been published. They have indicated significant gaps in data and prediction methods, notably for transition boiling, inverted annular film boiling and the minimum film boiling point. This paper reports on the more recent experimental and analytical post-CHF studies. An assessment of the available prediction methods is made and recommendation for use in current reactor thermohydraulic codes are offered. The effect of geometry (bundle vs. tube), rod-spacing devices, flow orientation, etc. are discussed and ad hoc correction factors are proposed.

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Authors and Affiliations

  1. Service des Transferts Thermiques, Centre d’Etudes Nucléaires de Grenoble, Commissariat à l’Energie Atomique, Grenoble, France

    D. C. Groeneveld & J. C. Rousseau

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  1. D. C. Groeneveld
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  2. J. C. Rousseau
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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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Groeneveld, D.C., Rousseau, J.C. (1983). CHF and Post-CHF Heat Transfer : An Assessment of Prediction Methods and Recommendations for Reactor Safety Codes. 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_11

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  • DOI: https://doi.org/10.1007/978-94-009-6845-5_11

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