NUCLEAR TECHNIQUES, Volume. 46, Issue 7, 070606(2023)

Development of flow blockage model for core heat transfer and its application in QUENCH experiment

Pengcheng GAO1,2, Bin ZHANG2、*, Hao YANG2, and Jianqiang SHAN2
Author Affiliations
  • 1Naval Research Institute, Beijing 100071, China
  • 2School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China
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    References(22)

    [1] Repetto G, Dominguez C, Durville B et al. The R&D PERFROI project on thermal mechanical and thermal hydraulics behaviors of a fuel rod assembly during a Loss Of Coolant Accident[C](2015).

    [4] Williams E, Martin R, Gandrille P et al. Recent revisions to MAAP4 for U.S. EPR severe accident applications[C](2008).

    [5] Gauntt R O C J E, Cole R K. MELCOR computer code manuals 1-2[R](2005).

    [15] Pettersson K, Chung H, Billone M et al. Nuclear fuel behaviour in loss-of-coolant accident (LOCA) conditions[R](2010).

    [16] Grandjean C. A state-of-the-art review of past programs devoted to fuel behaviour under LOCA conditions - Part one: clad swelling and rupture assembly flow blockage[R](2005).

    [17] Idelchik I E, Fried E[M]. Handbook of hydraulic resistance(2008).

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    Pengcheng GAO, Bin ZHANG, Hao YANG, Jianqiang SHAN. Development of flow blockage model for core heat transfer and its application in QUENCH experiment[J]. NUCLEAR TECHNIQUES, 2023, 46(7): 070606

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    Paper Information

    Category: Research Articles

    Received: Mar. 29, 2022

    Accepted: --

    Published Online: Aug. 3, 2023

    The Author Email:

    DOI:10.11889/j.0253-3219.2023.hjs.46.070606

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