NUCLEAR TECHNIQUES, Volume. 46, Issue 5, 050605(2023)

Thermal-mechanical characteristics of helical cruciform fuel bundle

Tenglong CONG1, Yujie LIU2, Hui GUO1, Yao XIAO1, and Hanyang GU1、*
Author Affiliations
  • 1School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
  • 2College of Nuclear Science and Technology, Harbin Engineering University, Harbin 150009, China
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    Figures & Tables(23)
    Sketch for the single fuel rod and the self-support structure (a) Single fuel rod, (b) Self-support structure
    Cross section of the HCF assembly for PWR designed by Lightbridge
    Computational domain of the rod bundle (a) 3D view of the rod bundle, (b) Cross section at the 90°, 180°, 270° plane, (c) Dimension of a single rod
    Mesh partitioning of a single fuel(a) Mesh of the single rod, (b) Mesh of the axial section
    Distribution of von Mises stress on the center rod
    Temperature, von Misesstress and strain at the 180° plane (a) Temperature distribution, (b) von Mises stress distribution, (c) Plastic strain distribution, (d) Elastic strain distribution, (e) Thermal strain distribution
    Distributions of stress components on the outer surface of cladding at the 180° plane (the bold scale line represents the zero stress scale)
    Distributions of von Mises stress and plastic strain on the cladding outer surface with different helical angles (a) von Misesstress (the bold scale line means the zero stress scale), (b) Plastic strain
    Temperature distribution on the cladding inner and outer surfaces at 180° plane under different operating conditions
    Distributions of von Mises stress and plastic strain on the cladding inner and outer surfaces at 180° plane under different operating conditions (a) von Mises stress (the bold scale line means the zero stress scale), (b) Plastic strain
    Stress intensification curves for cladding material under different temperature
    Variations of fuel power and temperature at different monitoring points (a) Locations of the monitoring points, (b) Power and temperature variations
    Stress at the cladding inner and outer surfaces of blade tip under reactivity insertion accident (a) Cladding inner surface, (b) Cladding outer surface
    Plastic strain at the cladding inner and outer surfaces of blade tip under reactivity insertion accident (a) Cladding inner surface, (b) Cladding outer surface
    Stress at the cladding inner and outer surfaces of blade elbow under reactivity insertion accident (a) Cladding inner surface, (b) Cladding outer surface
    Temperature at the cladding inner and outer surfaces of blade elbow under reactivity insertion accident (a) Cladding inner surface, (b) Cladding outer surface
    Variations of core pressure and power under the LOCA condition
    Stress at the cladding inner and outer surfaces of blade tip under the LOCA condition (a) Cladding inner surface, (b) Cladding outer surface
    Plastic strain at the cladding inner and outer surfaces of blade tip under the LOCA condition (a) Cladding inner surface, (b) Cladding outer surface
    Stress at the cladding inner and outer surfaces of blade elbow under the LOCA condition (a) Cladding inner surface, (b) Cladding outer surface
    Plastic strain at the cladding inner and outer surfaces of blade elbow under the LOCA condition (a) Cladding inner surface, (b) Cladding outer surface
    • Table 1. Heat transfer boundary under steady conditions

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      Table 1. Heat transfer boundary under steady conditions

      工况

      Conditions

      冷却剂入口温度

      Coolant temperature at the inlet

      / K

      冷却剂入口速度

      Coolant velocity at the inlet

      / m∙s-1

      单根燃料体积释热率

      Volume heat rate of a single rod

      / MW∙m-3

      单相工况Single-phase condition553.851740
      两相工况Two-phase condition617.9
    • Table 2. Time sequence of the events for transient accidents

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      Table 2. Time sequence of the events for transient accidents

      事故类型

      The type of accidents

      时间

      Time / s

      事件

      Events

      反应性引入事故Reactivity initiated accident1事故发生Accident happens
      1.1

      控制棒完全弹出堆芯并触发停堆信号

      Control rod is completely ejected out of the core and trip signal is sent

      2吸收棒开始下落Absorber rod begins dropping
      5吸收棒完全插入堆芯Absorber rod is fully inserted into the core

      一回路压力边界破口失水事故Loss of coolant

      accidents at primary circuit pressure boundary

      1事故发生Accident happens
      1.6触发低压停堆信号Trip signal is sent because of low pressure
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    Tenglong CONG, Yujie LIU, Hui GUO, Yao XIAO, Hanyang GU. Thermal-mechanical characteristics of helical cruciform fuel bundle[J]. NUCLEAR TECHNIQUES, 2023, 46(5): 050605

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    Paper Information

    Category: Research Articles

    Received: Jul. 13, 2022

    Accepted: --

    Published Online: Jun. 30, 2023

    The Author Email:

    DOI:10.11889/j.0253-3219.2023.hjs.46.050605

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