NUCLEAR TECHNIQUES, Volume. 46, Issue 6, 060604(2023)

Friction pressure drop model for wire-wrapped rod bundles in full flow

Taotao ZHOU1,2, Shuyong LIU1、*, and Jie YU1,2
Author Affiliations
  • 1Institute of Nuclear Energy Safety Technology, Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, China
  • 2University of Science and Technology of China, Hefei 230026, China
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    References(27)

    [15] Grazzini R, Tirelli D. Experimental determination of pressure drop of PEC reactor fuel element[R](1971).

    [16] Ohshima H, Imai Y. Numerical simulation method of thermal-hydraulics in wire-wrapped fuel pin bundle of sodium-cooled fast reactor[C], 453(2017).

    [26] Hoffmann H. Experimentelle Untersuchungen zur Kühlmittelquervermischung und zum Druckabfall in Stabbündel mit wendelf¨ormigen Abstandshaltern. Einflußder Ergebenisse auf die Auslegung von Brennelementen schneller natrium-gekühlter Reaktoren[D](1981).

    [27] CHEN Yiliang, ZHU Minming[M]. Physical fluid dynamics(2008).

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    Taotao ZHOU, Shuyong LIU, Jie YU. Friction pressure drop model for wire-wrapped rod bundles in full flow[J]. NUCLEAR TECHNIQUES, 2023, 46(6): 060604

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    Paper Information

    Category: Research Articles

    Received: Sep. 7, 2022

    Accepted: --

    Published Online: Jul. 5, 2023

    The Author Email:

    DOI:10.11889/j.0253-3219.2023.hjs.46.060604

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