Review and proposal for best fit of wire-wrapped fuel bundle friction factor and pressure drop predictions using various existing correlations |
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| Authors: | E. Bubelis M. Schikorr |
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| Affiliation: | Institute for Reactor Safety, Forschungszentrum Karlsruhe (FZK), DE-76344 Eggenstein-Leopoldshafen, Germany |
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| Abstract: | The aim of this paper is to provide an overview of the existing wire-wrapped fuel bundle friction factor/pressure drop correlations and to qualitatively evaluate which of the existing friction factor correlations are the best in retracing the results of a large set of the experimental data available on wire-wrapped fuel assemblies tested under different coolant conditions. |
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| Keywords: | BWR, boiling water reactor DHRS, decay heat removal system ETDR, experimental technology demonstration reactor FA, fuel assembly FM, flow meter GCFR, gas cooled fast reactor HX, heat exchanger LBE, lead-bismuth eutectic LWR, light water reactor PFBR, (Indian) prototype fast breeder reactor PWR, pressurized water reactor |
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