Separation of europium as a homologue of americium from high acidity solutions using a manufactured resin material

化学 无机化学 色谱法 离子 有机化学 锕系元素
作者
Yaxuan Zou,Jingju Li,Jiacan Su,Shirong Wang,Yin Su,Keliang Shi,Tonghuan Liu,Junqiang Yang,Xiaolin Hou,Jiangang He
出处
期刊:Separation and Purification Technology [Elsevier BV]
卷期号:: 126557-126557
标识
DOI:10.1016/j.seppur.2024.126557
摘要

Americium (Am), a radioactive element, is highly valued for its commercial uses. Its source is primarily derived from high-acid, high-radiation, and high-temperature high-level radioactive waste liquids, requiring materials that are capable of enduring the most intense conditions for its capture. For this challenging environment, we successfully created a composite material TODGA@SiO2 that is capable of effectively separating Am3+. An exhaustive evaluation of the material was undertaken, focusing on essential parameters and the column behavior of the material to ascertain its suitability for engineering applications. The composite is highly resistant to acid (>3 M HNO3), can withstand temperatures up to 200 °C, and is radiation resistant up to 200 kGy, making it a great choice. Highlighting its suitability for radioactive waste, the adsorbent exhibited outstanding stability even after being soaked in 3 M HNO3 for 11 days. In terms of performance, this material had a rapid kinetics (1 min, >95 %), a considerable adsorption capacity (Kd value close to 3 × 105 mL/g), and a high selectivity for Am3+. From a cost and environmental protection perspective, the adsorbent can be regenerated and reused at least five times, and the extractant structure adheres to the CHON (Carbon, Hydrogen, Oxygen, and Nitrogen) principle, so orderly disposal is simple. At the same time, the high column efficiency, with a recovery rate of Am3+ of more than 94 %, makes its industrial application highly practical. In comparison to existing adsorbents, the material reported in this work has shown greater efficacy, making it a suitable inorganic composite for Am3+ extraction from radioactive liquid waste.
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