Optimal ferro frit for leaching stability of radioactive metal oxide sludges-based solidified body

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Ki Joon Kang , Sia Hwang , Hee Reyoung Kim
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Abstract

In nuclear power plants, the corrosion of metallic components exposed to radioactive liquid waste and coolant can result in the formation of sludge. This study examined the optimization of ferro frit additives to enhance the leaching stability of solidified radioactive sludge. Specifically, simulated sludge, composed of Fe2O3, Cr2O3, NiO, and Co, was solidified using various additives—including ferro frit 3110, ferro frit 3195, and B2O3—and evaluated for leaching stability under ANSI/ANS 16.1 conditions. Among the four target elements, Fe, Ni, and Co consistently demonstrated excellent leaching resistance, while Cr required further immobilization. Co, a key nuclide in leaching resistance assessments for radioactive waste disposal, exhibited low leachate concentrations under all tested conditions. The addition of B2O3-rich frits substantially improved Cr leaching resistance by strengthening the glass network structure and suppressing ionic mobility. This improvement is attributed to B2O3's role in reducing non-bridging oxygen content and increasing network polymerization. As the Cr2O3 and NiO content in the sludge increased, the sintering temperature required for stable solidification rose from 950 to 1050 °C. These findings demonstrate that producing chemically durable solidified radioactive sludge suitable for final disposal requires both thermal and compositional optimization, particularly through the incorporation of B2O3.
放射性金属氧化物渣基固化体浸出稳定性的最佳铁渣
在核电站中,暴露于放射性废液和冷却剂的金属部件的腐蚀会导致污泥的形成。本研究对铁渣添加剂进行了优化,以提高固化放射性污泥的浸出稳定性。具体来说,模拟污泥由Fe2O3、Cr2O3、NiO和Co组成,使用各种添加剂(包括铁frit 3110、铁frit 3195和b2o3)固化,并在ANSI/ANS 16.1条件下评估浸出稳定性。在四个目标元素中,Fe、Ni和Co始终表现出优异的抗浸出性,而Cr需要进一步固定。Co是放射性废物处理抗浸出性评估的关键核素,在所有测试条件下均表现出较低的渗滤液浓度。富b2o3水果的加入通过强化玻璃网络结构和抑制离子迁移率显著提高了Cr的抗浸出能力。这种改善是由于B2O3降低了非桥氧含量和增加了网络聚合。随着污泥中Cr2O3和NiO含量的增加,稳定凝固所需的烧结温度从950℃升高到1050℃。这些发现表明,生产适合最终处置的化学持久固化放射性污泥需要热和成分优化,特别是通过B2O3的掺入。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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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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