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A particle-image velocimetry system for measurement of velocity flow fields for investigations of thermohydraulic processes on the large-scale benchmark of a promising fast-neutron reactor

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Abstract

The use of visualization techniques in the research on thermohydraulic processes using large-scale models of nuclear power plants is discussed. In particular, the original particle-image velocimetry (PIV) measurement system at the TISEI test bench was presented, which is a model of a proposed fast-neutron reactor. Illumination and video-filming systems with the simultaneous use of several lasers and camcorders, as well as image-processing algorithms that make it possible to carry out field measurements with high precision in a complex configuration of the reactor model, reflections and distortions of the laser knife section, and shadowing by obstacles are described. The developed methodology of conversion of the image coordinates and velocity field into the reference system of the reactor model using a virtual 3D simulation made it possible to significantly simplify the experiments.

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Authors and Affiliations

  1. Federal Research Center, Institute of Applied Physics, Russian Academy of Sciences, Nizhny Novgorod, 603950, Russia

    D. A. Sergeev, A. A. Kandaurov & Yu. I. Troitskaya

  2. Afrikantov Joint Stock Company, Experimental Design Bureau for Mechanical Engineering, Nizhny Novgorod, 603074, Russia

    V. V. Pakholkov, S. A. Rogozhkin & S. F. Shepelev

Authors
  1. D. A. Sergeev
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  2. A. A. Kandaurov
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  3. Yu. I. Troitskaya
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  4. V. V. Pakholkov
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  5. S. A. Rogozhkin
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  6. S. F. Shepelev
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Corresponding author

Correspondence to D. A. Sergeev.

Additional information

Original Russian Text © D.A. Sergeev, A.A. Kandaurov, Yu.I. Troitskaya, V.V. Pakholkov, S.A. Rogozhkin, S.F. Shepelev, 2017, published in Pribory i Tekhnika Eksperimenta, 2017, No. 3, pp. 119–128.

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Sergeev, D.A., Kandaurov, A.A., Troitskaya, Y.I. et al. A particle-image velocimetry system for measurement of velocity flow fields for investigations of thermohydraulic processes on the large-scale benchmark of a promising fast-neutron reactor. Instrum Exp Tech 60, 418–427 (2017). https://doi.org/10.1134/S0020441217020233

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