NUCLEAR TECHNIQUES, Volume. 46, Issue 5, 050605(2023)

Thermal-mechanical characteristics of helical cruciform fuel bundle

Tenglong CONG1, Yujie LIU2, Hui GUO1, Yao XIAO1, and Hanyang GU1、*
Author Affiliations
  • 1School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
  • 2College of Nuclear Science and Technology, Harbin Engineering University, Harbin 150009, China
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    References(18)

    [6] Conboy T M. Assessment of helical-cruciform fuel rods for high power density LWRs[D](2010).

    [9] Bauer A A E. An evaluation of the properties and behavior of zirconium-uranium alloys (Report No.BMI-1350)[R](1959).

    [11] Hofman G L, Leibowitz L, Kramer J M et al. Metallic fuels handbook[R](1985).

    [18] Todreas N E, Kazimi M S[M]. Nuclear systems Volume 1: thermal hydraulic fundamentals(2012).

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    Tenglong CONG, Yujie LIU, Hui GUO, Yao XIAO, Hanyang GU. Thermal-mechanical characteristics of helical cruciform fuel bundle[J]. NUCLEAR TECHNIQUES, 2023, 46(5): 050605

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    Paper Information

    Category: Research Articles

    Received: Jul. 13, 2022

    Accepted: --

    Published Online: Jun. 30, 2023

    The Author Email:

    DOI:10.11889/j.0253-3219.2023.hjs.46.050605

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