Shuffler中子质询系统核材料质量测量的基体校正方法

雍金龙; 宋玉收; 赵云龙; 侯英伟; 刘辉兰

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

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Shuffler中子质询系统核材料质量测量的基体校正方法

加速器技术、射线技术及应用 | 更新时间：2025-05-07

- Shuffler中子质询系统核材料质量测量的基体校正方法
- Matrix correction method for nuclear material mass measurement using Shuffler neutron interrogation system
- 核技术 2025年48卷第4期文章编号：040203
- 作者机构：
  
  哈尔滨工程大学核科学与技术学院哈尔滨 150001
- 作者简介：
  
  雍金龙，男，1996年出生，2021年于新疆大学获硕士学位，现为博士研究生，研究领域为核保障测量
  宋玉收，E-mail：songyushou80@163.com
- 基金信息：
  
  国家自然科学基金(12227810)
- DOI：10.11889/j.0253-3219.2025.hjs.48.240210
  中图分类号： TL816,⁺3
- 收稿日期：2024-04-10，
  
  修回日期：2024-07-12，
  
  纸质出版日期：2025-04-15
- 稿件说明：
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雍金龙,宋玉收,赵云龙等.,Shuffler中子质询系统核材料质量测量的基体校正方法[J].核技术,2025,48(04):040203.

YONG Jinlong,SONG Yushou,ZHAO Yunlong,et al.Matrix correction method for nuclear material mass measurement using Shuffler neutron interrogation system[J].NUCLEAR TECHNIQUES,2025,48(04):040203.
雍金龙,宋玉收,赵云龙等.,Shuffler中子质询系统核材料质量测量的基体校正方法[J].核技术,2025,48(04):040203. DOI： 10.11889/j.0253-3219.2025.hjs.48.240210. CSTR： 32193.14.hjs.CN31-1342/TL.2025.48.240210.

YONG Jinlong,SONG Yushou,ZHAO Yunlong,et al.Matrix correction method for nuclear material mass measurement using Shuffler neutron interrogation system[J].NUCLEAR TECHNIQUES,2025,48(04):040203. DOI： 10.11889/j.0253-3219.2025.hjs.48.240210. CSTR： 32193.14.hjs.CN31-1342/TL.2025.48.240210.

摘要

废物桶中基体材料的存在限制了主动质询系统对特殊核材料（Special Nuclear Material，SNM）质量测量的准确性，确保核保障测量结果不受基体材料的影响至关重要。因此，考虑到单位质量缓发中子计数率随SNM质量增加的变化，本文在传统校正方法的基础上开发了一种新的基体校正方法。为了验证新方法的有效性，利用Geant4工具包构建了WM3210 PAN Shuffler系统模型，针对常见的基体材料开展了校正算法研究。结果表明，对于不同富集度以及分布状态的U

材料，传统校正方法与新校正方法均可以有效地降低基体材料对核材料质量测量的影响。对于U

材料位于基体中心的情况，新

校正方法得到的

235

U质量平均相对偏差为13.6%，而传统方法的相对偏差为23.8%；对于U

材料均匀弥散在基体中的情况，新校正方法得到的

235

U质量平均相对偏差为7.78%，而传统方法的相对偏差为20.0%。表明新方法比传统方法表现出更好的校正能力。

Abstract

Background

Active neutron interrogation (ANI) measurement systems can quantify the fissile masses of special nuclear materials (SNMs) using neutrons and are widely used in nuclear safeguarding fields. However

different hydrogen densities effect the delayed neutron count rate differently

and the hydrogen-containing matrix in the waste drum weakens the signal of delayed neutrons and limits the fissile mass measurement precision of the ANI system.

Purpose

This study aims to improve the assay performance of the ANI system in nuclear safeguard measurements by developing a matrix correction method.

Methods

Based on the response of the flux monitor

a new matrix correction method was developed based on the conventional correction methods. A WM3210 PAN Shuffler system model was constructed using the Geant4 toolkit

and correction method was explored for common matrix materials. Finally

materials with different enrichments and distributions were applied to the effectiveness comparison between new correction method and the traditional method.

Results

The results show that for U

materials with different enrichments and distribution states

both the traditional correction method and the new correction method can effectively reduce the influence of the matrix material on the measurement of SNM mass. For the case where U

material is located at the center of the matrix

the average relative deviation of the

235

U mass obtained by the new correction method is 13.6%

while that of the traditional method is 23.8%. For the case where U

material is uniformly dispersed

in the matrix

the average relative deviation of

235

U mass obtained by the new correction method is 7.78% whilst that of the traditional method is 20.0%.

Conclusion

Results of this indicate that the new method demonstrates better correction capability than the traditional one.

关键词

Keywords

references

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