NUCLEAR TECHNIQUES, Volume. 48, Issue 7, 070019(2025)

Numerical simulation of thermal stratification characteristics in the upper plenum chamber of lead-based fast reactors

Yue WANG1,2, Xuanming LIU1,2, Fengchen LI3, Hongna ZHANG3, Shuqi MENG4, Xin WANG4, Yulong MAO4, Qian LI1,2, and Weihua CAI1,2、*
Author Affiliations
  • 1Laboratory of Thermo-Fluid Science and Nuclear Engineering, Northeast Electric Power University, Jilin 132012, China
  • 2School of Energy and Power Engineering, Northeast Electric Power University, Jilin 132012, China
  • 3School of Mechanical Engineering, Tianjin University, Tianjin 300072, China
  • 4China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen 518000, China
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    References(17)

    [17] Yoshikawa S, Minami M. Data description for coordinated research project on benchmark analyses of sodium natural convection in the upper plenum of the MONJU reactor vessel under supervisory of technical working group on fast reactors, International Atomic Energy Agency[R](2009).

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    Yue WANG, Xuanming LIU, Fengchen LI, Hongna ZHANG, Shuqi MENG, Xin WANG, Yulong MAO, Qian LI, Weihua CAI. Numerical simulation of thermal stratification characteristics in the upper plenum chamber of lead-based fast reactors[J]. NUCLEAR TECHNIQUES, 2025, 48(7): 070019

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    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: Dec. 24, 2024

    Accepted: --

    Published Online: Sep. 15, 2025

    The Author Email: Weihua CAI (CAIWeihua)

    DOI:10.11889/j.0253-3219.2025.hjs.48.240536

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