NUCLEAR TECHNIQUES, Volume. 47, Issue 11, 110604(2024)

Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics

Xu JI1,2, Xiang CHAI1,2, Lefu ZHANG1,2, and Xiaojing LIU1,2、*
Author Affiliations
  • 1School of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
  • 2Shanghai Digital Nuclear Reactor Technology Intergration Innovation Center, Shanghai 200240, China
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    Figures & Tables(11)
    Comparison of experiment values and simulation values under different working conditions
    Framework of neutronics-material-thermal-hydraulics coupling
    Flowchart of Newton-Krylov algorithm
    Geometry configuration of the single rod
    Dynamic changes of key coupling parameters over time under standard operating condition (a) Average thickness, (b) Maximum thickness, (c) Average removal thickness, (d) Average temperature, (e) Maximum temperature, (f) kinf
    Distribution contours of thickness of the oxide layers under standard operating condition (a) Thickness contour of magnetite layer, (b) Thickness contourof Fe-Cr spinel layer
    Dynamic changes of key coupling parameters over time under different oxygen concentrations (a) Average thickness,(b) Maximum thickness, (c) Average removal thickness, (d) Average temperature, (e) Maximum temperature, (f) kinf
    Distribution contours of thickness of the oxide layers for 10 000 h under different oxygen concentrations (a) Thickness contour of magnetite layer, (b) Thickness contour of Fe-Cr spinel layer
    • Table 1. Main parameters of the single rod

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      Table 1. Main parameters of the single rod

      参数

      Parameter

      Value

      燃料直径

      Radius of the fuel / mm

      8.5

      包壳厚度

      Thickness of the cladding / mm

      0.5
      栅距Pitch / mm11.4

      燃料高度

      Height of the fuel / mm

      900
      燃料材料Fuel materialMOX (24%PuO2+76%UO2)

      包壳材料

      Cladding material

      T91不锈钢

      T91 stainless steel

      冷却剂材料

      Coolant material

      LBE
      功率Power / W21 230
    • Table 2. Boundary conditions of standard operating condition

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      Table 2. Boundary conditions of standard operating condition

      物理场

      Physics field

      边界

      Boundary

      类型

      Type

      Value

      压力Pressure出口OutletDirichlet0 Pa
      速度Velocity出口OutletDirichlet1.5 m·s-1
      冷却剂壁面Coolant wallSymmetry
      包壳壁面Cladding wallDirichlet0 m·s-1
      温度Temperature入口InletDirichlet593 K
      中子Neutronics上、下端Top and bottomVacuum
    • Table 3. Meshing table

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      Table 3. Meshing table

      序号Number
      网格1 Mesh 1网格2 Mesh 2网格3 Mesh 3
      节点数Nodes9 88119 72139 101
      氧化层平均厚度Average thickness of oxide layers / μm1.4141.4101.410
      燃料最高温度Maxmium temperature of fuel / K1 654.551 628.921 624.567
      kinf1.325 011.327 421.327 46
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    Xu JI, Xiang CHAI, Lefu ZHANG, Xiaojing LIU. Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics[J]. NUCLEAR TECHNIQUES, 2024, 47(11): 110604

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    Paper Information

    Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING

    Received: Nov. 29, 2023

    Accepted: --

    Published Online: Jan. 2, 2025

    The Author Email: Xiaojing LIU (LIUXiaojing)

    DOI:10.11889/j.0253-3219.2024.hjs.47.110604

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