NUCLEAR TECHNIQUES, Volume. 48, Issue 7, 070001(2025)

Design features and application prospects of Tsinghua high flux reactor

Lei SHI, Heng XIE, Jian LI*, Zhihong LIU, and Ding SHE
Author Affiliations
  • Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China
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    Figures & Tables(5)
    Schematic diagram of THFR pressure vessel section (color online)
    Cross sectional schematic diagram of THFR reactor core (color online)
    Comparisons of neutron flux and irradiation capability of high flux reactors (color online)(a) Maximum total neutron flux, (b) High-quality irradiation capability
    • Table 1. Overall design parameters of THFR

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      Table 1. Overall design parameters of THFR

      参数

      Parameter

      数值

      Value

      反应堆功率 Reactor power / MWt80
      设计寿命 Design life / a60
      辐照孔道未扰平均热中子通量(E<1 eV) Unperturbed average thermal neutron flux in irradiation channel (E<1 eV) / n∙cm-2∙s-12.1×1015
      辐照孔道未扰平均快中子通量(E>100 eV)Unperturbed average fast neutron flux in irradiation channel (E>100 eV) / n∙cm-2∙s-12.0×1015
      材料(奥氏体不锈钢)辐照损伤剂量 Irradiation damage dose of material (austenitic stainless steel)/ dpa∙a-1≥15
      最大快中子辐照能力 Maximum fast neutron irradiation capability / dpa∙L∙a-1≥120
      燃料组件形式Fuel element type弧板型Arc plate type
      燃料组件芯体Fuel element coreU3Si2-Al
      首炉燃料235U富集度 235U enrichment in the first fuel loading / wt%19.75
      旋转控制鼓个数Number of rotation control drums6
      主冷却剂系统压力容器入口/出口压力(额定工况) Inlet/outlet pressure of the pressure vessel in the primary coolant system (rated condition) / MPa2.5/2.0
      堆芯活性区入口/出口平均温度(额定工况) Average temperature at the inlet/outlet of the reactor core active region (rated condition) / ℃35/62
      反应堆冷却剂流量(额定工况) Reactor coolant flow rate (rated condition) / t∙h-14 320
      主换热器数量Number of main heat exchangers4
    • Table 2. Parameter comparisons of main high flux reactors in the world

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      Table 2. Parameter comparisons of main high flux reactors in the world

      参数ParameterHFIRATRSM-3HFETRJHRTHFR
      总功率 Total Power / MWt8525010012510080
      堆芯最大功率密度 Maximum power density of the reactor core / kW∙L-13 4854 35310 0002 0343 0122 500
      燃料最大表面热负荷 Maximum surface heat load of fuel element / MW∙m-25.337.03>103.565.04.4

      反应堆状态

      Reactor status

      运行Operational运行Operational运行Operational运行Operational在建Under construction计划建设Planned construction
      最大热中子通量(E<0.625 eV) Maximum thermal neutron flux / n∙cm-2∙s-12.3×1015 (有靶With targets)1.0×10155.0×10156.2×10144.3×10143.2×1015;2.6×1015 (有靶With targets)
      最大快中子通量 Maximum fast neutron flux/ n∙cm-2∙s-1

      2.2×1015(E>100 eV);

      1.4×1015(E>0.1 MeV)

      5.0×1014

      (E>1 MeV)

      2.3×1015

      (E>0.1 MeV)

      1.7×1015

      (E>0.625 eV)

      1.0×1015(E>0.1 MeV);

      5.5×1014(E>0.907 MeV)

      2.9×1015 (E>0.625 eV);2.6×1015 (E>100 eV);

      1.7×1015 (E>0.1 MeV);

      8.0×1014 (E>1 MeV)

      最大总中子通量 Maximum total neutron flux / n∙cm-2∙s-15.6×10152.75×10155.4×10152.3×10152.0×10155.7×1015
      最大材料辐照损伤 Maximum material irradiation damage/ dpa∙a-1141016~255~1010≥15
      单个循环长度 Single fuel cycle length / d21~2350~6010~14282530
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    Lei SHI, Heng XIE, Jian LI, Zhihong LIU, Ding SHE. Design features and application prospects of Tsinghua high flux reactor[J]. NUCLEAR TECHNIQUES, 2025, 48(7): 070001

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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: Jan. 26, 2025

    Accepted: --

    Published Online: Sep. 15, 2025

    The Author Email: Jian LI (LIJian)

    DOI:10.11889/j.0253-3219.2025.hjs.48.250043

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