Upcycling waste borosilicate glass (BS) is a viable and sustainable way of preserving the natural resources required for the production of new materials and ensuring environmental sanitation and safety. This study was aimed at investigating how the addition of BS influences the physical, chemical, and mechanical properties and shielding performance against neutrons and charged particles on metakaolin-based geopolymer G. Four batches of G infused with 10%, 20%, and 30% wt BS samples and coded as G, G-10BS, G-20BS, and G-30BS, respectively, were fabricated based on the solid-state reaction method. The samples were characterized accordingly using experimental and theoretical procedures. X-ray diffraction analysis of the materials showed that the addition of BS suppressed crystal peaks in the geopolymers. The Vickers hardness values were calculated as 554, 503, 517, and 528 HV under a 0.1 kg load. The values of fast neutron macroscopic cross-section increased from 0.0601 cm to 0.0706 cm as BS content increased from 0 to 30 wt%. The coherent, incoherent, absorption, and total interaction probabilities of thermal neutrons increased in the geopolymer samples. For electrons, the stopping powers were in the range of 1.575–13.17 cm/g, 1.571–13.15 cm/g, 1.571–13.16 cm/g, and 1.571–13.18 cm2/g for G, G-10BS, G-20BS, and G-30BS, respectively. The projected ranges of carbon ions in G, G-10BS, G-20BS, and G-30BS are within the limits 0.069–17.87 μm, 0.064–16.99 μm, 0.064–16.99 μm, and 0.057–15.24 μm. The trend of the projected ranges of electrons, protons, α-particles, and C ions with kinetic energies within 15 keV and 15 MeV was mostly in the sequence G > G-10BS > G-20BS > G-30BS. This order was consistent with the density and BS content of the geopolymer samples. The addition of BS to the metakaolin-based geopolymer improved the fast neutron moderating capacity and thermal neutron cross-sections and reduced the range of charged particle radiation in the geopolymers. The neutron shielding ability of G-30BS was found to be better than that of some existing shielding materials. The BS-infused concrete can be useful for the production of concrete used for radiation control.

中文翻译：

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含硼硅酸盐废玻璃的偏高岭土基聚合物的物理、化学和辐射屏蔽性能


回收废硼硅酸盐玻璃（BS）是保护新材料生产所需的自然资源并确保环境卫生和安全的可行且可持续的方式。本研究旨在研究BS的添加如何影响偏高岭土基地质聚合物G的物理、化学和机械性能以及对中子和带电粒子的屏蔽性能。四批注入10%、20%和30%的G基于固相反​​应方法制备了wt BS样品，并分别编码为G、G-10BS、G-20BS和G-30BS。使用实验和理论程序对样品进行相应的表征。材料的 X 射线衍射分析表明，BS 的添加抑制了地质聚合物中的晶体峰。 0.1 kg 负载下的维氏硬度值计算为 554、503、517 和 528 HV。随着BS含量从0wt%增加到30wt%，快中子宏观截面值从0.0601cm增加到0.0706cm。地质聚合物样品中热中子的相干、非相干、吸收和总相互作用概率增加。对于电子，G、G-10BS、G-20BS 的阻止本领在 1.575–13.17 cm/g、1.571–13.15 cm/g、1.571–13.16 cm/g 和 1.571–13.18 cm2/g 范围内。和G-30BS，分别。 G、G-10BS、G-20BS 和 G-30BS 中碳离子的预计范围在 0.069–17.87 μm、0.064–16.99 μm、0.064–16.99 μm 和 0.057–15.24 μm 的范围内。动能在15 keV和15 MeV范围内的电子、质子、α粒子和C离子的预计射程变化趋势大多为G>G-10BS>G-20BS>G-30BS。该顺序与地质聚合物样品的密度和 BS 含量一致。 在偏高岭土基地质聚合物中添加BS提高了地质聚合物的快中子慢化能力和热中子截面，并减少了带电粒子辐射范围。研究发现G-30BS的中子屏蔽能力优于一些现有的屏蔽材料。 BS注入混凝土可用于生产用于辐射控制的混凝土。