NUCLEAR TECHNIQUES, Volume. 46, Issue 5, 050603(2023)

Core neutron source generation method for nuclear reactor shielding calculation

Pingxun ZHANG, Bin ZHANG*, and Yixue CHEN
Author Affiliations
  • School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China
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    Figures & Tables(9)
    Neutron importance of core for the pressure vessel in the NUREG/CR-6115 model
    Flow chart of geometric grid source assignment
    Geometric grid source mapping method (a) Geometric grid segmentation, (b) Sub-grid source calculation, (c) Geometric grid source assignment
    Geometric diagram of the NUREG/CR-6115 benchmark model 1-Core baffle, 2-Core barrel, 3-Inner inlet water gap, 4-Thermal shield, 5-Reactor pressure vessel liner, 6-Air gap, 7-Pressure vessel insulation, 8-Biological shield liner
    Source distribution of the NUREG/CR-6115 model (a) Average source calculation algorithm, (b) Multi-weight source mesh mapping algorithm
    Neutron spectrum distribution on internal surface of pressure vessel (a) Axial peak location, (b) RPV lower weld location
    Axial-normalized relative power distribution of the NUREG/CR-6115 model
    • Table 1. Root mean square (RMS) of the relative error for fast neutron fluence in reactor pressure vessel (E>1.0 MeV)

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      Table 1. Root mean square (RMS) of the relative error for fast neutron fluence in reactor pressure vessel (E>1.0 MeV)

      位置

      Location

      RMS / %
      ARES-DORTARES-MCNP

      多权重源强网格

      映射算法

      Multi-weight source

      mesh mapping

      algorithm

      平均源强

      计算方法

      Average source

      calculation

      algorithm

      多权重源强网格

      映射算法

      Multi-weight source mesh

      mapping algorithm

      平均源强

      计算方法

      Average source

      calculation

      algorithm

      轴向峰值处

      Axial peak location

      内表面Internal surface13.046 412.241 53.537 47.171 2
      1/4壁厚1/4 thickness13.145 813.185 35.746 610.242 5
      1/2壁厚1/2 thickness14.386 215.652 6

      焊缝处

      Lower weld location

      内表面Internal surface13.271 621.819 72.722 121.183 1
      1/4壁厚1/4 thickness13.257 524.758 0
      1/2壁厚1/2 thickness14.371 429.691 0
    • Table 2. Influence of neutron source distribution

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      Table 2. Influence of neutron source distribution

      位置Location外围组件源强层级数Peripheral component source levels
      012
      1.0 MeV0.1 MeV1.0 MeV0.1 MeV1.0 MeV0.1 MeV
      反应堆压力容器内表面Reactor pressure vessel internal surface20.61%19.64%0.43%-0.01%-0.01%-0.01%
      反应堆压力容器1/4壁厚Reactor pressure vessel 1/4 thickness20.78%19.84%0.47%0.00%-0.01%0.00%
      反应堆压力容器1/2壁厚Reactor pressure vessel 1/2 thickness20.77%19.79%0.46%-0.01%-0.01%-0.01%
      反应堆压力容器3/4壁厚Reactor pressure vessel 3/4 thickness20.62%19.67%0.45%-0.01%-0.01%-0.01%
      反应堆压力容器外表面Reactor pressure vessel outside surface20.64%19.58%0.45%-0.01%0.00%-0.01%
      平均值Average20.68%19.70%0.45%-0.01%-0.01%-0.01%
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    Pingxun ZHANG, Bin ZHANG, Yixue CHEN. Core neutron source generation method for nuclear reactor shielding calculation[J]. NUCLEAR TECHNIQUES, 2023, 46(5): 050603

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    Paper Information

    Category: Research Articles

    Received: Jul. 7, 2022

    Accepted: --

    Published Online: Jun. 30, 2023

    The Author Email:

    DOI:10.11889/j.0253-3219.2023.hjs.46.050603

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