Status and perspective of turbulence heat transfer modelling for the industrial application of liquid metal flows

Ferry Roelofs*, Afaque Shams, Ivan Otic, Michael Böttcher, Matthieu Duponcheel, Yann Bartosiewicz, Djamel Lakehal, Emilio Baglietto, Sylvain Lardeau, Xu Cheng

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

85 Scopus citations

Abstract

Liquid metal cooled reactors are envisaged to play an important role in the future of nuclear energy production because of their possibility to use natural resources efficiently and to reduce the volume and lifetime of nuclear waste. Typically, sodium and lead(-alloys) are envisaged as coolants for such reactors. Obviously, in the development of these reactors, thermal-hydraulics is recognized as a key (safety) challenge. A fundamental issue to this respect is the modelling of turbulent heat flux over the complete range from natural, mixed and convection to forced convection regimes. Current engineering tools apply statistical turbulence closures and adopt the concept of the turbulent Prandtl number based on the Reynolds analogy. This analogy is valid mainly for forced convective flows with Prandtl number of order of unity. In the particular case of liquid metal, where the Prandtl number is less than 1, the turbulent Prandtl number concept is not applicable and robust engineering turbulence models are needed. Thus, a model is required which can deal with all flow regimes simultaneously in liquid metal flows. In the framework of the European project THINS (thermal-hydraulics for innovative nuclear systems), some promising routes for improvements have been identified and are currently under evaluation.

Original languageEnglish
Pages (from-to)99-106
Number of pages8
JournalNuclear Engineering and Design
Volume290
DOIs
StatePublished - 22 Jul 2015
Externally publishedYes

Bibliographical note

Funding Information:
The work described in this paper was funded by the FP7 EC Collaborative Project THINS No. 249337. The authors wish to acknowledge the support of all colleagues involved.

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • General Materials Science
  • Nuclear Energy and Engineering
  • Safety, Risk, Reliability and Quality
  • Waste Management and Disposal
  • Mechanical Engineering

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