NUCLEAR TECHNIQUES, Volume. 46, Issue 12, 120603(2023)

Sensitivity analysis of large leakage sodium-water reaction protection system critical parameters with paralleling steam generators in a sodium-cooled fast reactor

Xi BAI1, Peiwei SUN1、*, Gang LUO2, Huasong CAO3, and Xinyu WEI1
Author Affiliations
  • 1School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China
  • 2Nuclear Power Institute of China, Chengdu 610012, China
  • 3Xi'an Thermal Power Research Institute Co. Ltd, Xi'an 710054, China
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    References(15)

    [5] Bell . TRANSWRAP: a code for analyzing the system effects of large-leak sodium water reactions in LMFBR steam generators[J]. Lecture Notes in Electrical Engineering, 124-135(1974).

    [12] HOU Bin. Research of steam generator protection system design and verification teat in the demonstration fast reactor[D](2020).

    [13] Gerber A, Pirus J P, Beils S et al. Safety improvement research to design a sodium fast reactor steam generator with regard to sodium/water reaction risk[C], 667-680(2010).

    [14] XIANG Yang. Simulating method and analysis of the sodium-water reaction accident in the sodium-cooled fast reactor[D](2019).

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    Xi BAI, Peiwei SUN, Gang LUO, Huasong CAO, Xinyu WEI. Sensitivity analysis of large leakage sodium-water reaction protection system critical parameters with paralleling steam generators in a sodium-cooled fast reactor[J]. NUCLEAR TECHNIQUES, 2023, 46(12): 120603

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    Paper Information

    Category: Research Articles

    Received: May. 26, 2023

    Accepted: --

    Published Online: Mar. 7, 2024

    The Author Email: Peiwei SUN (孙培伟)

    DOI:10.11889/j.0253-3219.2023.hjs.46.120603

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