• NUCLEAR TECHNIQUES
  • Vol. 47, Issue 10, 100601 (2024)
Hanyuan GONG1, Binhang ZHANG2,3,*, Yonghong ZHANG2, Haibo TANG2, and Xianbao YUAN2
Author Affiliations
  • 1College of Mechanical and Power Engineering, China Three Gorges University, Yichang 443002, China
  • 2College of Science, China Three Gorges University, Yichang 443002, China
  • 3Key Laboratory of Advanced Nuclear Energy Design and Safety, Ministry of Education, Hengyang 421200, China
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    DOI: 10.11889/j.0253-3219.2024.hjs.47.100601 Cite this Article
    Hanyuan GONG, Binhang ZHANG, Yonghong ZHANG, Haibo TANG, Xianbao YUAN. Comparison of neutron transport calculation methods based on C5G7-MOX and preliminary analysis of sensitivity of MOC parameters[J]. NUCLEAR TECHNIQUES, 2024, 47(10): 100601 Copy Citation Text show less
    Diagram of method of characteristics (MOC)
    Fig. 1. Diagram of method of characteristics (MOC)
    Quadrant division and interface labeling
    Fig. 2. Quadrant division and interface labeling
    Diagram of C5G7-MOX assembly layout
    Fig. 3. Diagram of C5G7-MOX assembly layout
    Structural diagram C5G7-MOX cell
    Fig. 4. Structural diagram C5G7-MOX cell
    Diagram of C5G7-MOX fuel rod layou
    Fig. 5. Diagram of C5G7-MOX fuel rod layou
    Flowchart of MOC based on DRAGON
    Fig. 6. Flowchart of MOC based on DRAGON
    Memory overhead for different grids and polar angles
    Fig. 7. Memory overhead for different grids and polar angles
    Total time consumptions for different grids and polar angles
    Fig. 8. Total time consumptions for different grids and polar angles
    Calculation errors under different grids and polar angles
    Fig. 9. Calculation errors under different grids and polar angles
    Normalized cell power distribution in OpenMC
    Fig. 10. Normalized cell power distribution in OpenMC
    Normalized cell power distribution in DRAGON
    Fig. 11. Normalized cell power distribution in DRAGON

    计算方法

    Computing method

    耗时

    Elapsed time / min

    内存开销

    Memory overhead / MB

    相对误差

    Relative error / 10-5

    MOC23.937.560.4
    CP1 355.615 291.161.4
    IC374.11 233.43 899.6
    Table 1. 2D C5G7-MOX fuel assembly calculation results

    参数类型

    Parameter type

    选择区间

    Selection interval

    极角类型Polar angle typeGAUS、LCMD、CACB
    极角数目Number of polar angles2、3
    方位角Azimuth angles8、12、16、30、32、64
    线密度Linear density / cm-18、10、12、15、20
    网格划分Mesh generation2×2、4×4、6×6、8×8
    Table 2. Parameter type and selection interval

    方位角

    Azimuth

    angles

    耗时

    Elapsed time

    / s

    内存开销

    Memory

    overhead / kB

    相对误差

    Relative error

    / 10-5

    8890.06268 49251.16
    121 345.66271 33621.83
    161 729.97281 76613.23
    302 671.79271 2025.90
    322 723.28271 0565.90
    642 537.84271 4125.90
    Table 3. Calculation results under different azimuth angles

    特征线密度

    Characteristic linear densities / cm-1

    耗时

    Elapsed time / s

    内存占用

    Memory overhead / kB

    相对误差

    Relative error / 10-5

    81 807.41271 38214.16
    102 409.81272 80810.87
    122 662.86271 2685.90
    152 856.16273 49222.50
    203 487.05282 89412.30
    Table 4. Calculation results obtained under different characteristic linear densities
    Hanyuan GONG, Binhang ZHANG, Yonghong ZHANG, Haibo TANG, Xianbao YUAN. Comparison of neutron transport calculation methods based on C5G7-MOX and preliminary analysis of sensitivity of MOC parameters[J]. NUCLEAR TECHNIQUES, 2024, 47(10): 100601
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