含硼富镁核屏蔽尾矿的屏蔽性能及屏蔽机理研究

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Mengge Dong , G. Lakshminarayana , Xuefei Zhang , Xiangxin Xue
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引用次数: 0

摘要

含硼富镁尾矿的高效利用是硼工业可持续发展面临的重要挑战。本研究提出了一种创新的方法来重新利用bcmrt作为屏蔽材料,并系统地研究了它们对热中子/快中子和伽马射线的屏蔽性能和潜在机制。研究结果表明,bcmrt表现出优异的热中子衰减,仅用1厘米的材料就能实现高达100%的屏蔽效率,从而超过某些市售屏蔽的性能。然而,进一步的优化是必要的,以提高它们对快中子和伽马射线的效率。中子衰减机制主要受低能段硼的吸收作用支配,中能段高原子序数元素通过弹性散射参与,高能段弹性散射和非弹性散射共同参与。伽马射线衰减机制主要受高原子序数元素的支配,在不同的能量范围内具有不同的核相互作用。给出了窄束和宽束伽玛射线在0.001-100,000 MeV范围内的综合衰减参数。该研究为bcmrt在先进屏蔽材料开发中的潜在应用提供了重要见解。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Investigation of shielding properties and mechanisms of boron-containing magnesium-rich tailings for nuclear shielding application
Efficient utilization of boron-containing magnesium-rich tailings (BCMRTs) represents a critical challenge for the sustainable development of boron industry. This study introduces an innovative approach to repurpose BCMRTs as shielding materials and systematically investigates their shielding properties and underlying mechanisms against thermal/fast neutrons, and gamma rays. The findings demonstrate that BCMRTs exhibit exceptional thermal neutron attenuation, achieving a shielding efficiency of up to 100 % with merely 1 cm of material, thereby surpassing the performance of certain commercially available shields. However, further optimization is necessary to enhance their efficiency against fast neutrons and gamma rays. Neutron attenuation mechanism is predominantly governed by absorption effect of boron in low-energy range, elements with higher atomic number contribute in middle energy range through elastic scattering, and both elastic and inelastic scattering in high energy range. Gamma ray attenuation mechanism is predominantly governed by elements with high atomic number, with distinct nuclear interactions dominating across various energy ranges. Furthermore, comprehensive attenuation parameters for both narrow-beam and wide-beam gamma rays within the 0.001–100,000 MeV range are presented. This research provides critical insights into the potential application of BCMRTs in the development of advanced shielding materials.
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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