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2 Publications

Experimental analysis of crossflow in the reactor core geometry.

Kliem, M.

Abstract

A new method for the thermal-hydraulic calculations in the reactor core using a porous media approach is presented in this paper.
The Core Crossflow Experimental Facility (CCEF) was built for the validation of this method.
The comparison of the calculations using this method with the experimental data from CCEF are also presented.

Keywords: reactor core; crossflow; CCEF

  • Lecture (Conference)
    Annual Meeting on Nuclear Technology 2002, Stuttgart, Germany, May 14-16, 2002 Proceedings pp. 55-58
  • Contribution to proceedings
    Annual Meeting on Nuclear Technology 2002, Stuttgart, Germany, May 14-16, 2002 Proceedings pp. 55-58

Permalink: https://www.hzdr.de/publications/Publ-4257

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