NUCLEAR TECHNIQUES, Volume. 46, Issue 10, 100602(2023)

Systematic measurement method for primary coolant flow rate in advanced passive nuclear power units

Hui LUO*
Author Affiliations
  • Shandong Nuclear Power Corporation, Yantai 265116, China
  • show less
    References(15)

    [2] LING Xing. Analysis for the method to the reactor coolant system flowrate measurement in the nuclear power plant[C], 745-749(2009).

    [3] YANG Hongxu. Application of bend pipe flowmeter in the primary loop of Sanmen nuclear power plant[J]. Nuclear Power Engineering and Technology, 10-13(2012).

    [5] LIN Zhijian. Determination of reactor coolant flowrate for Qinshan nuclear power plant[J]. Nuclear Power Engineering, 14, 42-45(1993).

    [8] ZHU Lei. Numerical simulation of water flow characteristics and experimental study on flow coefficient of elbow flowmeter[D](2008).

    [15] CHEN Yongwei, LIU Runfeng, ZHOU Xinxing. Reactor coolant system and loop flow correction method[P].

    Tools

    Get Citation

    Copy Citation Text

    Hui LUO. Systematic measurement method for primary coolant flow rate in advanced passive nuclear power units[J]. NUCLEAR TECHNIQUES, 2023, 46(10): 100602

    Download Citation

    EndNote(RIS)BibTexPlain Text
    Save article for my favorites
    Paper Information

    Category: Research Articles

    Received: Jun. 10, 2023

    Accepted: --

    Published Online: Nov. 21, 2023

    The Author Email:

    DOI:10.11889/j.0253-3219.2023.hjs.46.100602

    Topics