NUCLEAR TECHNIQUES, Volume. 46, Issue 11, 110603(2023)

Validation of an in-house system analysis code for heat pipe cooled reactor

Pan WU, Zeyu OUYANG, Yu ZHU, and Jianqiang SHAN*
Author Affiliations
  • School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China
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    Figures & Tables(19)
    Design diagram of kilopower heat pipe reactor
    Model framework of TAPIRS-D program
    Relationship curve between the reactivity value of control drum and the turning angle
    Diagram of radial partitioning of the core
    Diagram of the standard heat pipe "flat front" startup model
    Heat transfer model of heat pipe in normal operation (a) Heat pipe one-dimensional thermal resistance network model, (b) Improved two-dimensional thermal resistance network model
    Diagram of KRUSTY core layout (a) Cross-sectional view of reactor, (b) Physical view of reactor
    Structure diagram of self-passed arterial sodium heat pipe
    Diagram of KRUSTY core modeling
    Validation results for KRUSTY start-up condition
    Verification results of load reduction condition (a) Core fission power transients, (b) Fuel assembly temperature transients
    Validation results for load increase conditions (a) Core fission power transients, (b) Fuel assembly temperature transients
    Validate results of heat pipe failure accident (a) Core fission power transients, (b) Fuel assembly temperature transients
    Parametric response of Stirling thermoelectric conversion under negative reactivity introduction accident(a) Core fission power transients, (b) Fuel assembly temperature transients
    Validate results of positive reactivity introduction (a) Core fission power transients, (b) Fuel assembly temperature transients
    Validation results for loss of heat sink accident (a) Core fission power transients, (b) Fuel assembly temperature transients
    • Table 1. SAIRS-C heat pipe reactor key parameters

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      Table 1. SAIRS-C heat pipe reactor key parameters

      中子参数Neutron parameters数值Value
      λ / 1·s-10.012 73, 0.031 75, 0.116, 0.311 8, 1.399, 3.876
      Α (βi/β)0.037, 0.211, 0.187, 0.407, 0.131, 0.027
      Λ / s5.5×10-8
    • Table 2. KRUSTY reactor main parameters

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      Table 2. KRUSTY reactor main parameters

      参数Parameters数值Value参数Parameters数值Value
      堆芯直径Reactor core diameter / cm11热管数量Number of heat pipes8
      堆芯高度Reactor core height / cm25热管工质Working fluid of heat pipeNa
      燃料元件数目Number of fuel elements3工作温度Operating temperature / ℃720~800
      燃料总质量Total fuel mass / kg32.2热管外径Heat pipe outer diameter / cm1.27

      B4C控制棒直径

      B4C control rod diameter / cm

      4.0热管壁厚Heat pipe wall thickness / cm0.089
      最大热功率Maximum thermal power / kW5.0蒸发段长度Length of evaporation section / cm35.6
      名义热功率Nominal thermal power / kW3.0绝热段长度Length of adiabatic section / cm86.4
      输出电功率Output electric power / kW1.0冷凝段长度Length of condensing section / cm8.89

      堆芯平均温度

      Average core temperature / ℃

      800管壁材料Container materialHaynes230
      燃耗(FIMA)Fuel burnup (FIMA)0.000 01%吸液芯材料Wick materialStainless 316
      堆芯材料Fuel materialU-8Mo

      冷凝段平均温度

      Average temperature of condensing section / ℃

      ~775
      Mo质量分数Mo mass fraction7.8%斯特林机数目Number of Stirling machines8
      U-235富集度U-235 enrichment93.1%斯特林机型号Stirling machine modelASC E2-7、E2-8
    • Table 3. Steady state result comparison

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      Table 3. Steady state result comparison

      T=7.5 h,Qcold=295 W

      实验数据

      Experimental data

      计算结果

      Calculation results

      相对误差

      Relative error / %

      堆芯裂变功率

      Reactor core fission power / W

      2 750.02 723.80.95

      燃料表面平均温度

      Average fuel surface temperature / ℃

      800.0801.80.22
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    Pan WU, Zeyu OUYANG, Yu ZHU, Jianqiang SHAN. Validation of an in-house system analysis code for heat pipe cooled reactor[J]. NUCLEAR TECHNIQUES, 2023, 46(11): 110603

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    Paper Information

    Category: Research Articles

    Received: Apr. 5, 2023

    Accepted: --

    Published Online: Dec. 23, 2023

    The Author Email:

    DOI:10.11889/j.0253-3219.2023.hjs.46.110603

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