• NUCLEAR TECHNIQUES
  • Vol. 47, Issue 2, 020202 (2024)
Haoran ZHANG1、2, Yan ZHANG1、2、*, Wenxing HU1、2, Jinhui QU2, Shiliang LIU3, and Renbo WANG2、3
Author Affiliations
  • 1Fundamental Science on Radioactive Geology and Exploration Technology Laboratory, East China University of Technology, Nanchang 330013, China
  • 2Engineering Research Center for Nuclear Technology Application, Ministry of Education, East China University of Technology, Nanchang 330013, China
  • 3Pan-China Detect Technology Co., Ltd., Nanchang 330013, China
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    DOI: 10.11889/j.0253-3219.2024.hjs.47.020202 Cite this Article
    Haoran ZHANG, Yan ZHANG, Wenxing HU, Jinhui QU, Shiliang LIU, Renbo WANG. Simulation study of uranium content in uranium yellow cake using the active multiplicity method[J]. NUCLEAR TECHNIQUES, 2024, 47(2): 020202 Copy Citation Text show less
    Schematic diagram of the active multiplicity method for measuring the total mass of uranium in yellow cake
    Fig. 1. Schematic diagram of the active multiplicity method for measuring the total mass of uranium in yellow cake
    FH-NCM/S1 device model established by the MCNP program (a) 2D axis section view, (b) 3D axis section view
    Fig. 2. FH-NCM/S1 device model established by the MCNP program (a) 2D axis section view, (b) 3D axis section view
    Flow chart of MCNP and MATLAB joint simulation multiplicity analysis flow chart
    Fig. 3. Flow chart of MCNP and MATLAB joint simulation multiplicity analysis flow chart
    fDi versus mass of 238U in the sample
    Fig. 4. fDi versus mass of 238U in the sample
    Diagram of the relationship between multiplicity count rates S/D/T and the change of sample mass
    Fig. 5. Diagram of the relationship between multiplicity count rates S/D/T and the change of sample mass
    Relationship between the calculated and actual values of the sample induced fission rate and multiplication with uranium content (a) Sample induced fission rate, (b) Simulated multiplication M and calculated net leakage multiplication ML
    Fig. 6. Relationship between the calculated and actual values of the sample induced fission rate and multiplication with uranium content (a) Sample induced fission rate, (b) Simulated multiplication M and calculated net leakage multiplication ML
    Actual and measured values of the corrected fission rate F and total mass of uranium m(a) Change of sample fission rate F and Fm′ with mass of 238U, (b) Calculated value and actual value of total uranium mass
    Fig. 7. Actual and measured values of the corrected fission rate F and total mass of uranium m(a) Change of sample fission rate F and Fm′ with mass of 238U, (b) Calculated value and actual value of total uranium mass
    Relation diagram of the change of sample S/D rate with water content (a) Single rate S, (b) Double rate D
    Fig. 8. Relation diagram of the change of sample S/D rate with water content (a) Single rate S, (b) Double rate D
    Correction curve and double rate before and after correction(a) Correction curve fitting, (b) Double rate before and after correction
    Fig. 9. Correction curve and double rate before and after correction(a) Correction curve fitting, (b) Double rate before and after correction
    Actual and measured values of total uranium mass in samples with different water contents
    Fig. 10. Actual and measured values of total uranium mass in samples with different water contents
    属性 Parameter值 Value
    3He阵列圈数 3He array turns4
    3He管根数 Number of 3He tubes80
    装置整体探测效率(252Cf)Detection efficiency41%
    探测器中子衰减时间 Die-away time55 μs
    样品腔大小 Sample chamber size⌀20.0 cm×20.0 cm
    Table 1. Main parameters of FH-NCM/S1

    中子源类型

    Neutron source

    nDnDifi / %
    241Am-Li22 527 328566 8521.01
    241Am-Be18 756 956767 9101.64
    Table 2. Excitation efficiency and detection efficiency of the fission of yellow cake material excited by 241Am-Li and 241Am-Be
    Haoran ZHANG, Yan ZHANG, Wenxing HU, Jinhui QU, Shiliang LIU, Renbo WANG. Simulation study of uranium content in uranium yellow cake using the active multiplicity method[J]. NUCLEAR TECHNIQUES, 2024, 47(2): 020202
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