Comparison of experimental and simulation results on interior subchannel of a 61-pin wire-wrapped hexagonal fuel bundle

N. Goth, P. Jones, D. T. Nguyen, R. Vaghetto, Y. A. Hassan, A. Obabko, E. Merzari, Paul F. Fischer

Research output: Contribution to conferencePaperpeer-review

3 Scopus citations

Abstract

As part of a joint U.S. Department of Energy project, AREVA, Argonne National Laboratory, Terrapower, and Texas A&M University have collaborated to produce experimental data and computational results to characterize the flow behavior of a 61-pin wire-wrapped hexagonal fuel bundle. Isothermal experiments have been performed at TAMU to characterize the flow behaviors along the near-wall and interior subchannels by applying particle image/tracking velocimetry techniques. In this paper, comparisons are made between particle image velocimetry velocity field measurements to Argonne National Laboratory’s large-eddy simulation results at an interior subchannel for a Reynolds number of 19,000. It can be concluded the shape and magnitude of the mean vertical velocity component are in excellent agreement for the selected horizontal line plots. Maximum relative errors are less than 10% until the subchannel walls are approached. The shape, and to a lesser extent, magnitude of the mean horizontal velocity component are in satisfactory agreement between the particle image velocimetry and large-eddy simulation results.

Original languageEnglish
StatePublished - 2017
Externally publishedYes
Event17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017 - Xi'an, Shaanxi, China
Duration: Sep 3 2017Sep 8 2017

Conference

Conference17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017
Country/TerritoryChina
CityXi'an, Shaanxi
Period09/3/1709/8/17

Funding

This work was performed for the Department of Energy under contract DE-NE0008321.

FundersFunder number
U.S. Department of EnergyDE-NE0008321

    Keywords

    • Comparison of experimental
    • Flow characterization
    • Hexagonal fuel bundle
    • Simulation results
    • Sodium cooled fast reactor
    • Thermal hydraulics

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