NUCLEAR TECHNIQUES, Volume. 47, Issue 7, 070601(2024)

Coupled irradiation-thermal-mechanical analysis of fuel in solid core of heat pipe cooled reactor

Xuan YANG1, Quan LI2, Chenxi LI2, Jing ZHANG1、*, Yingwei WU1、**, Yanan HE1, Kailun GUO1, Guanghui SU1, Wenxi TIAN1, and Suizheng QIU1
Author Affiliations
  • 1School of Energy and Power Engineering, Xi'an Jiaotong University, Xi'an 710049, China
  • 2Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China
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    Figures & Tables(11)
    Schematic diagram of solid core structure and calculation unit selection
    Coupled irradiation-thermal-mechanical model of solid core
    Boundary condition and numbering setting for coupled irradiation-thermal-mechanical model (a) Boundary condition, (b) Heat pipe and fuel numbering scheme
    Steady-state temperature distribution contour of solid core fuel
    Steady-state stress distribution contour of solid core fuel
    Minimum gap between pellet and cladding (a), between monolith and cladding (b), between monolith and HP (c) varying with running time
    Variation of maximum temperature of pellet with running time
    Creep of monolith and cladding at operation period of 2 000 d (a) Monolith, (b) Monolith and cladding
    Variation of strain on the outer wall of cladding #7
    • Table 1. Geometric parameter and material of solid core

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      Table 1. Geometric parameter and material of solid core

      参数Parameters参数范围Parameter range数值Value
      燃料孔直径Fuel channel hole outer diameter / mm10~3019.5
      燃料棒之间间距Fuel-to-fuel pitch / mm10~4022.0
      燃料包壳厚度Fuel cladding thickness / mm1~21.5
      热管孔直径HP hole diameter / mm10~3020.5
      热管包壳厚度Pipe wall thickness / mm1~21.5
      芯块材料Fuel materialUO2UO2
      基体、包壳材料Monolith, cladding material316不锈钢Stainless 316316不锈钢Stainless 316
    • Table 2. Calculation parameter for solid core

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      Table 2. Calculation parameter for solid core

      计算参数Calculation parameters值Values
      芯块功率密度Power density / W·cm-310
      寿期Cycle length / a5
      UO2密度Density of UO2 / g·cm-310.52
      UO2质量Mass of UO2 / kg210
      燃耗Burnup / MWd·kgU-12
      热管运行温度HP isothermal temperature / ℃675
      燃料棒填充气体Rod fill gasHe
      气隙压力Gas pressure / MPa2
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    Xuan YANG, Quan LI, Chenxi LI, Jing ZHANG, Yingwei WU, Yanan HE, Kailun GUO, Guanghui SU, Wenxi TIAN, Suizheng QIU. Coupled irradiation-thermal-mechanical analysis of fuel in solid core of heat pipe cooled reactor[J]. NUCLEAR TECHNIQUES, 2024, 47(7): 070601

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    Paper Information

    Category: Research Articles

    Received: Dec. 28, 2023

    Accepted: --

    Published Online: Aug. 27, 2024

    The Author Email: ZHANG Jing (章静), WU Yingwei (巫英伟)

    DOI:10.11889/j.0253-3219.2024.hjs.47.070601

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