用于快中子和热中子屏蔽的新型地聚合物材料

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Jianxin Zhou , Alexander Fields , Shaffer Bauer , Ali Ozer , Waltraud M. Kriven , Angela Di Fulvio
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引用次数: 0

摘要

在这项工作中,我们通过将高达50%的聚乙烯(PE)和碳化硼(B4C)粉末分散到钾基GP (KGP)基体中,开发了用于中子屏蔽应用的新型地聚合物(GP)复合材料。我们使用自发裂变252Cf源和聚变氘氚发生器测量了它们对快中子的衰减系数,并使用慢化252Cf源测量了它们对热中子的衰减系数。基于pe的KGP旨在通过中子-氢碰撞降低中子的一次能量,而B4C中的10B则用于捕获和停止热中子。50% PE-KGP的快中子屏蔽性能较好,对裂变中子的衰减系数比高密度混凝土高30%。以B4C为基础的KGP配方,B4C重量为25%和50%,分别比商用含硼柔性材料高出约18%和50%。在模拟中,我们将KGP与PE和B4C分散剂混合使用。由50% PE-KGP和50% B4C-KGP组成的原型材料在减少剂量方面明显优于重晶石,这是由于基于裂变的光谱,类似于在核反应堆中发现的。此外,KGP具有优异的粘接性能、耐高温性能,可以成型成任何尺寸或形状,也可以进行3D或4D打印。因此,PE和b4c负载的KGP及其相关制造技术可以有效地应用于核电厂和其他依赖强中子源的设施,显著提高其安全性和成本效益。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Novel geopolymer materials for fast and thermal neutron shielding
In this work, we developed novel geopolymer (GP) composites for neutron shielding applications by dispersing up to 50 wt% polyethylene (PE) and boron carbide (B4C) powders into a potassium-based GP (KGP) matrix. We measured their attenuation coefficients to fast neutrons using a spontaneous fission 252Cf source and a fusion deuterium–tritium generator and to thermal neutrons using a moderated 252Cf source. The PE-based KGP were designed to reduce the neutron primary energy through neutron–hydrogen collisions, while 10B in B4C was exploited to capture and stop thermal neutrons. The fast-neutron shielding properties of 50 wt% PE-KGP were superior, with an attenuation coefficient to fission neutrons up to 30% higher than that of high-density concrete. The B4C-based KGP formulation with B4C at 25 wt% and 50 wt% outperforms commercial boron-loaded flexible materials by approximately 18% and 50%, respectively. In simulation, we combined KGP with PE and B4C dispersants. A prototypical material comprised of 50 wt% PE-KGP and 50 wt% B4C-KGP significantly outperformed barite in reducing the dose due to fission-based spectra, similar to those found at nuclear reactors. Additionally, KGP shows excellent adhesive properties, high-temperature resistance, and can be molded into any size or shape, as well as 3D or 4D printed. Therefore, PE and B4C-loaded KGP and associated manufacturing techniques can be effectively employed in nuclear power plants and other facilities that rely on intense neutron sources, significantly enhancing their safety and cost-effectiveness.
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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