Turbulent vortex trains in narrow square arrayed rod bundles of a dual-cooled nuclear reactor

Taehwan Kim, Kyung Min Kim, Ji Yeul Bae, Chang Hwan Shin, Wang Kee In, Hyung Hee Cho

Research output: Contribution to journalArticle

1 Citation (Scopus)

Abstract

The dual-cooled nuclear reactor is currently considered for improving the designs of current/future nuclear reactors. Investigation of the thermal-hydraulic characteristics of the nuclear reactor via experiments is essential for commercializing the dual-cooled nuclear reactor. In this paper, the turbulent flow in square arrayed six-rod bundles in the form of magnified copies of the dual-cooled and current OPR-1000 nuclear reactor is experimentally investigated by means of hot-wire anemometry and smoke-wire generation methods. Vortex trains which do not exist in an ordinary reactor subchannel are presented in the subchannel of the dual-cooled reactor. The vortices are induced by a span-wise velocity gradient. This flow pulsation phenomenon increases the inter-channel mixing of the subchannel. To understand the periodic feature of the pulsation, axial/cross velocities are measured and the periodic characteristic frequencies are obtained by a Fast Fourier Transform (FFT) analysis. The peak frequency that represents the quasi-periodic pulsation of the flow is increased with an increase in the axial velocity while the wavelength of the pulsation remains constant within a tested range of the Reynolds number (9000-51000). The vortex trains are highly synchronized with each other, as confirmed by means of visualization.

Original languageEnglish
Pages (from-to)2143-2149
Number of pages7
JournalScience China Technological Sciences
Volume56
Issue number9
DOIs
Publication statusPublished - 2013 Sep 1

All Science Journal Classification (ASJC) codes

  • Materials Science(all)
  • Engineering(all)

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