沸石和硅灰作为硼酸盐放射性废物胶凝固化的增强剂

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Xinfeng Liu , Chunguang Li , Zhimeng Yao , Shengdong Zhang , Zhenzhong Liu , Longcheng Liu , Tianle Li
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引用次数: 0

摘要

低、中水平硼酸盐放射性废液是核电站运行和退役过程中产生的常见废液。这些废物对环境安全和公众健康构成重大风险,必须采用有效的固化方法进行安全处置。在本研究中,研究了使用沸石和硅灰作为添加剂来提高胶结废物的性能。对五种配方进行了抗压强度、抗冲击性、抗冻融性、抗伽马辐照性、抗浸渍性和抗浸出性的评估。结果表明,10%沸石和5%硅灰(Z10-SF5)的组合在恶劣环境条件下(包括冻融循环、伽马辐射和浸泡)显著改善了固化形式的废物的机械性能和耐久性。结果还显示出出色的抗浸出能力,与对照相比,硼的累积浸出率降低了65%。x射线衍射(XRD)、扫描电镜(SEM)和压汞法(MIP)分析表明,添加剂促进了C-S-H凝胶的形成,改善了固化形态的孔隙结构和密度。这些发现突出了沸石和硅灰在促进硼酸盐放射性废物长期稳定方面的潜力。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Zeolite and silica fume as enhancers for cementitious solidification of borate radioactive waste
Low- and medium-level borate radioactive liquid wastes are common liquid wastes generated during the operation and decommissioning of nuclear power plants. These wastes pose significant risks to environmental safety and public health, necessitating effective solidification methods for safe disposal. In this study, the use of zeolite and silica fume as additives to increase the performance of cemented forms of waste was investigated. Five formulations were evaluated for compressive strength, impact resistance, freeze‒thaw resistance, gamma irradiation resistance, immersion resistance, and leaching resistance. The results indicate that the combination of 10 % zeolite and 5 % silica fume (Z10-SF5) significantly improved the mechanical properties and durability of the solidified forms of waste under harsh environmental conditions, including freeze‒thaw cycles, gamma irradiation, and immersion. The results also exhibited outstanding leaching resistance, reducing the cumulative boron leaching fraction by 65 % compared with that of the control. X-ray diffraction (XRD), scanning electron microscopy (SEM), and mercury intrusion porosimetry (MIP) analyses revealed that the additives promoted C-S-H gel formation and improved the pore structure and density of the solidified form. These findings highlight the potential of zeolite and silica fume in advancing the long-term stabilization of borate radioactive waste.
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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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