Matrix correction method for nuclear material mass measurement using Shuffler neutron interrogation system

Jinlong YONG; Yushou SONG; Yunlong ZHAO; Yingwei HOU; Huilan LIU

doi:10.11889/j.0253-3219.2025.hjs.48.240210

NUCLEAR TECHNIQUES, Volume. 48, Issue 4, 040203(2025)

Matrix correction method for nuclear material mass measurement using Shuffler neutron interrogation system

Jinlong YONG, Yushou SONG^*, Yunlong ZHAO, Yingwei HOU, and Huilan LIU

Author Affiliations

College of Nuclear Science and Technology, Harbin Engineering University, Harbin 150001, China

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Figures & Tables(10)

Fig. 1. Diagram of simulation model of WM3210 PAN Shuffler system (a) Side view, (b) Top view

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Fig. 2. Schematic illustration of WM3210 PAN Shuffler system (a) Background count measurement, (b) Transfer and irradiation of interrogation source, (c) Return of interrogation source and delayed neutron counting

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Fig. 3. For the 93.2%-enriched U₃O₈ material, the variation trend of the unit ²³⁵U mass delayed neutron count rate ( $K$ ) with in ²³⁵U material mass ( $m$ ), the dashed line represents the fitted curve using the logarithmic function

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Fig. 4. An average relative deviation in the mass of ²³⁵U when the U₃O₈ material as located at the center of the matrix (a) 0.7%-enriched U₃O₈ material, (b) 2%-enriched U₃O₈ material, (c) 3%-enriched U₃O₈ material

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Fig. 5. An average relative deviation in mass of ²³⁵U when U₃O₈ is homogeneously dispersed throughout the matrix (a) 0.7%-enriched U₃O₈, (b) 2%-enriched U₃O₈, (c) 3%-enriched U₃O₈

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Table 1. Physical properties of standard sample

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Table 1. Physical properties of standard sample

样品编号

Sample ID

材料

Material

物理特性

Physical property

相对丰度

Relative enrichment

密度

Density / g·cm^-3

质量

Mass / g

直径

Diameter / cm

高度

Hight / cm

²³⁵U / %

²³⁸U / %

UM1

U₃O₈

2.50

4.67

7.00

0.048 5

93.2

6.8

UM2

U₃O₈

2.50

1.25~250.21

7.00

0.013~2.600

94.5

5.5

Table 2. Main performances of the system model

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Table 2. Main performances of the system model

参数 Parameter	模拟值 Simulation value	参考值 Reference value	相对偏差 Relative deviation / %
²⁵²Cf中子源的探测效率 Detector efficiency for ²⁵²Cf neutron source / %	21.5	19.5^[16]	10.30
缓发中子探测效率 Detector efficiency for delayed neutron / %	26.3	25.9^[16]	1.54
缓发中子占裂变中子总数的比率 The ratio of delayed neutron account for total fission neutron / %	1.57	1.60^[17]	1.88
单位²³⁵U质量的缓发中子数 Delayed neutron count rate per unit mass²³⁵U / s^-1·g^-1	2.70	2.60^[10]	3.85

Table 3. Physical properties of matrix material

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Table 3. Physical properties of matrix material

材料 Material	ρ Density / g·cm^-3	$ρ_{H}$ Hydrogen density / g·cm^-3	质量 Mass / kg	填充高度 Fill height / cm
空气 Air	0.001 2	~ 0 ¹⁾	~ 0	76.85
聚乙烯刨花 Polystyrene，PS	0.059 9	0.008 57	11.63
蛭石聚乙烯混合物Vermiculite-polyethylene composite，VPS	0.148 4	0.021 2	28.77
聚乙烯管Polyethylene，PT	0.216 8	0.031 0	42.03
聚乙烯块Polyethylene，PC	0.464 1	0.066 3	89.96

Table 4. Delayed neutron count rate per unit uranium mass for the U₃O₈ based on different ²³⁵U enrichments and matrix materials

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Table 4. Delayed neutron count rate per unit uranium mass for the U₃O₈ based on different ²³⁵U enrichments and matrix materials

材料 Material	单位铀质量缓发中子计数率 Delayed neutron counting rate per unity uranium mass / s^-1·mg^-1
	3%富集度²³⁵U 3%-enriched ²³⁵U		2%富集度²³⁵U 2%-enriched ²³⁵U		0.7%富集度²³⁵U 0.7%-enriched ²³⁵U
	计数率 Counting rate	RSD Relative standard deviation / %	计数率 Counting rate	RSD Relative standard deviation / %	计数率 Counting rate	RSD Relative standard deviation / %
Air	238.51	0.06	210.98	0.08	187.27	0.05
PS	966.90	0.13	827.52	0.09	359.66	0.12
VPS	2 259.59	0.09	1 552.44	0.07	611.30	0.07
PT	1 332.17	0.07	940.82	0.08	375.83	0.08
PC	50.71	0.17	37.55	0.07	15.61	0.11

Table 5. $R$ values and flux-monitor count rates for various hydrogen densities in matrix calculated using Geant4 toolkit

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Table 5. $R$ values and flux-monitor count rates for various hydrogen densities in matrix calculated using Geant4 toolkit

基体材料 ( $ρ_{H}$ ) Matrix material	R	通量监视器计数率 Flux monitor counting rate / s^-1
基体材料 ( $ρ_{H}$ ) Matrix material	R	Cd管 Cd tube	RSD Relative standard deviation	裸管 Bare tube	RSD Relative standard deviation
Air (~ 0)	1.12	5.99×10⁵	6.75×10^-3	6.70×10⁵	6.70×10^-3
PS (0.008 57)	1.69	7.31×10⁵	5.14×10^-3	1.24×10⁶	4.56×10^-3
VPS (0.021 2)	2.55	7.62×10⁵	7.07×10^-3	1.94×10⁶	6.96×10^-3
PT (0.031 0)	2.90	7.28×10⁵	5.38×10^-3	2.11×10⁶	4.36×10^-3
PC (0.066 3)	3.02	6.26×10⁵	1.14×10^-2	1.89×10⁶	3.36×10^-3

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Jinlong YONG, Yushou SONG, Yunlong ZHAO, Yingwei HOU, Huilan LIU. Matrix correction method for nuclear material mass measurement using Shuffler neutron interrogation system[J]. NUCLEAR TECHNIQUES, 2025, 48(4): 040203

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Paper Information

Category: ACCELERATOR, RAY TECHNOLOGY AND APPLICATIONS

Received: Apr. 10, 2024

Accepted: --

Published Online: Jun. 3, 2025

The Author Email: Yushou SONG (宋玉收)

DOI:10.11889/j.0253-3219.2025.hjs.48.240210

Topics

laser devices and laser physics

Lasers and Laser Optics

Laser physics

laser manufacturing

Instrumentation, Measurement and Metrology

Table 1. Physical properties of standard sample

Table 1. Physical properties of standard sample

Table 2. Main performances of the system model

Table 2. Main performances of the system model

Table 3. Physical properties of matrix material

Table 3. Physical properties of matrix material

Table 4. Delayed neutron count rate per unit uranium mass for the U3O8 based on different 235U enrichments and matrix materials

Table 4. Delayed neutron count rate per unit uranium mass for the U3O8 based on different 235U enrichments and matrix materials

Table 5. R values and flux-monitor count rates for various hydrogen densities in matrix calculated using Geant4 toolkit

Table 5. R values and flux-monitor count rates for various hydrogen densities in matrix calculated using Geant4 toolkit

Table 4. Delayed neutron count rate per unit uranium mass for the U₃O₈ based on different ²³⁵U enrichments and matrix materials

Table 4. Delayed neutron count rate per unit uranium mass for the U₃O₈ based on different ²³⁵U enrichments and matrix materials

Table 5. $R$ values and flux-monitor count rates for various hydrogen densities in matrix calculated using Geant4 toolkit

Table 5. $R$ values and flux-monitor count rates for various hydrogen densities in matrix calculated using Geant4 toolkit