NUCLEAR TECHNIQUES, Volume. 48, Issue 4, 040610(2025)

Analysis of load following capability for small fluoride-salt-cooled high- temperature advanced reactor

Xindi LYU1, Dalin ZHANG1、*, Xinyu LI1, Yu LIANG2, Jian DENG2, Suizheng QIU1, and Guanghui SU1
Author Affiliations
  • 1School of Energy and Power Engineering, Xi'an Jiaotong University, Xi'an 710049, China
  • 2Nuclear Power Institute of China, Chengdu 610213, China
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    References(20)

    [4] Fratoni M. Development and applications of methodologies for the neutronic design of the Pebble Bed Advanced High Temperature Reactor (PB-AHTR)[D](2008).

    [5] Shi J, Aufiero M, Fratoni M. Sensitivity and uncertainty analysis of the Pebble-Bed Fluoride-saltcooled High-temperature Reactor (PB-FHR)[C], 3624-3635(2018).

    [11] Macdonald R. Investigation and design of a secure, transportable fluoride-salt-cooled high-temperature reactor (TFHR) for isolated locations[D](2014).

    [17] XU Bo. The thermal hydraulic design and accident analyses of small module solid fuel fluoride salt reactor TMSR-SF2[D](2017).

    [18] ZHANG Jianmin[M]. Nuclear reactor control(2002).

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    Xindi LYU, Dalin ZHANG, Xinyu LI, Yu LIANG, Jian DENG, Suizheng QIU, Guanghui SU. Analysis of load following capability for small fluoride-salt-cooled high- temperature advanced reactor[J]. NUCLEAR TECHNIQUES, 2025, 48(4): 040610

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    Paper Information

    Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING

    Received: May. 10, 2024

    Accepted: --

    Published Online: Jun. 3, 2025

    The Author Email: Dalin ZHANG (张大林)

    DOI:10.11889/j.0253-3219.2025.hjs.48.240185

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