NUCLEAR TECHNIQUES, Volume. 48, Issue 7, 070021(2025)

Numerical simulation of liquid lithium flow heat transfer in the rod bundle channel

Shuo LIU, Wenshu LI, Zhao JIN, Chenglong WANG*, Dalin ZHANG, and Suizheng QIU
Author Affiliations
  • Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China
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    Figures & Tables(15)
    Cross-section diagram of SP-100 core
    Schematic diagram of a single component rod bundle channel
    Meshing of single component rod bundle channel structure
    Schematic diagram of Takahashi's experimental section
    Model validation associated with Nu and Pe
    Temperature contour in the middle section of the rod bundle channel (color online)
    Variation of convective heat transfer coefficient with Pe
    Influence of Peclet number (Pe)on Nusselt number (Nu)
    Influence of heat flux on Nusselt number (Nu)
    Influence of heat flux on outlet temperature (color online)
    Velocity contour in the middle section of the rod bundle channel (color online)
    Influence of Peclet number (Pe) on pressure drop
    • Table 1. Overall design parameter of SP-100

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      Table 1. Overall design parameter of SP-100

      参数Parameters数值Number
      反应堆热功率Reactor thermal power / kWt455
      反应堆电功率Reactor electrical power / kWe100
      反应堆进口温度Reactor inlet temperature / K1 310
      反应堆出口温度Reactor outlet temperature / K1 350
    • Table 2. Geometric parameters of rod bundle channel

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      Table 2. Geometric parameters of rod bundle channel

      结构参数Geometric parameters数值Number
      棒束数量Number of rods61
      单棒外径Fuel rod diameter / mm7.86
      单棒长度Fuel rod length / mm394
      棒间距Fuel rod pitch / mm8.80
    • Table 3. Grid independence validation

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      Table 3. Grid independence validation

      序号No.网格数量Mesh number努塞尔数Nusselt number
      163w0.168
      2102w0.176
      3208w0.177
      4297w0.178
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    Shuo LIU, Wenshu LI, Zhao JIN, Chenglong WANG, Dalin ZHANG, Suizheng QIU. Numerical simulation of liquid lithium flow heat transfer in the rod bundle channel[J]. NUCLEAR TECHNIQUES, 2025, 48(7): 070021

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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: Nov. 11, 2024

    Accepted: --

    Published Online: Sep. 15, 2025

    The Author Email: Chenglong WANG (WANGChenglong)

    DOI:10.11889/j.0253-3219.2025.hjs.48.240452

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