NUCLEAR TECHNIQUES, Volume. 48, Issue 7, 070031(2025)

Numerical simulation analysis and experimental validation for the reactor cavity of molten salt reactor

Mudan MEI1,2, Chong ZHOU1,2、*, Yang ZOU1,2、**, Yao FU1,2、***, and Naxiu WANG1,2
Author Affiliations
  • 1Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
  • 2University of Chinese Academy of Sciences, Beijing 100049, China
  • show less
    References(21)

    [20] Kim Hyun-Ju, Chi Se-Hwan, Kim Eung-Seon et al. Comparison of the thermal conductivity of selected nuclear graphite grades for high temperature gas-cooled reactor[C], 1-2.

    [22] ZHAO Hangbin. Research and application of a multiscale coupled model for the reactor cavity cooling system of high temperature gas-cooled reactor[D](2018).

    Tools

    Get Citation

    Copy Citation Text

    Mudan MEI, Chong ZHOU, Yang ZOU, Yao FU, Naxiu WANG. Numerical simulation analysis and experimental validation for the reactor cavity of molten salt reactor[J]. NUCLEAR TECHNIQUES, 2025, 48(7): 070031

    Download Citation

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

    Category: Special Issue on The First Academic Annual Conference of the Research Reactor and Innovative Reactor Association of Chinese Nuclear Society and Advanced Nuclear Power System Reactor Engineering

    Received: Nov. 8, 2024

    Accepted: --

    Published Online: Sep. 15, 2025

    The Author Email: Chong ZHOU (ZHOUChong), Yang ZOU (ZOUYang), Yao FU (FUYao)

    DOI:10.11889/j.0253-3219.2025.hjs.48.240424

    Topics