Optimization and shielding design of a thermal neutron device based on D-D neutron generator with Geant4 toolkit

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes Pub Date : 2024-08-26 DOI:10.1016/j.apradiso.2024.111483

Guang Yang , Rui Shi , Jianbo Yang , Xianguo Tuo

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引用次数: 0

Abstract

Neutron activation analysis is a highly sensitive non-destructive testing technique with important applications in industry, geoscience, medical therapy, etc. This work designed and optimized a thermal neutron device that utilized a portable D-D neutron generator, and the Monte Carlo method with the Geant4 toolkit was applied to simulation. The objective of the optimized design is to maximize the thermal neutron flux at the output surface and increase the utilization efficiency of the neutron generator. A parameter K was defined as a measure of the device's slowing capacity for neutrons and was used to determine the optimized device geometry. The simulation considered the contribution of different types and sizes of moderators and reflectors to the thermal neutron intensity to obtain the optimal size. The shielding protection of the device was then designed. The effectiveness of shielding with different thicknesses was evaluated using three dose reference points. The results indicated that the optimized device can achieve a maximum thermal neutron flux of 1.97 × 10⁵ n∙cm⁻²∙s⁻¹ at the output surface by using high-density polyethylene (HDPE) as the moderator and nickel as the reflector. It was determined that using 45 cm of HDPE and 9 cm of lead protection in sequence along the neutron head axis would reduce the dose rate at the reference point, located 5 cm from the surface of the device, below the safety limit of 2.5 μSv/h.

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利用 Geant4 工具包对基于 D-D 中子发生器的热中子装置进行优化和屏蔽设计

中子活化分析是一种高灵敏度的无损检测技术，在工业、地球科学、医疗等领域有着重要应用。这项研究设计并优化了一种利用便携式 D-D 中子发生器的热中子装置，并利用 Geant4 工具包的蒙特卡罗方法进行了模拟。优化设计的目标是使输出表面的热中子通量最大化，并提高中子发生器的利用效率。参数 K 被定义为设备中子慢化能力的量度，用于确定优化的设备几何形状。模拟考虑了不同类型和尺寸的慢化剂和反射器对热中子强度的贡献，以获得最佳尺寸。然后设计了装置的屏蔽保护。利用三个剂量参考点对不同厚度的屏蔽效果进行了评估。结果表明，通过使用高密度聚乙烯（HDPE）作为慢化剂和镍作为反射器，优化后的装置可在输出表面获得 1.97 × 105 n∙cm-2∙s-1 的最大热中子通量。据测定，沿中子头轴线依次使用 45 厘米的高密度聚乙烯和 9 厘米的铅保护层，可将距离装置表面 5 厘米的参考点处的剂量率降至 2.5 μSv/h 的安全限值以下。

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来源期刊

Applied Radiation and Isotopes 工程技术-核科学技术

CiteScore

3.00

自引率

12.50%

发文量

406

审稿时长

13.5 months

期刊介绍： Applied Radiation and Isotopes provides a high quality medium for the publication of substantial, original and scientific and technological papers on the development and peaceful application of nuclear, radiation and radionuclide techniques in chemistry, physics, biochemistry, biology, medicine, security, engineering and in the earth, planetary and environmental sciences, all including dosimetry. Nuclear techniques are defined in the broadest sense and both experimental and theoretical papers are welcome. They include the development and use of α- and β-particles, X-rays and γ-rays, neutrons and other nuclear particles and radiations from all sources, including radionuclides, synchrotron sources, cyclotrons and reactors and from the natural environment. The journal aims to publish papers with significance to an international audience, containing substantial novelty and scientific impact. The Editors reserve the rights to reject, with or without external review, papers that do not meet these criteria. Papers dealing with radiation processing, i.e., where radiation is used to bring about a biological, chemical or physical change in a material, should be directed to our sister journal Radiation Physics and Chemistry.