Fast and Efficient Removal of Uranium onto a Magnetic Hydroxyapatite Composite: Mechanism and Process Evaluation

The exploration and rational design of easily separable and highly efficient sorbents with satisfactory capability of extracting radioactive uranium (U)-containing compound(s) are of paramount significance. In this study, a novel magnetic hydroxyapatite (HAP) composite (HAP@ CoFe<sub>2</sub...

Descripción completa

Guardado en:
Detalles Bibliográficos
Autores principales: Tao Ou, Hairong Peng, Minhua Su, Qingpu Shi, Jinfeng Tang, Nan Chen, Diyun Chen
Formato: article
Lenguaje:EN
Publicado: MDPI AG 2021
Materias:
Acceso en línea:https://doaj.org/article/c4d95a81f800450cae6924a88867ebeb
Etiquetas: Agregar Etiqueta
Sin Etiquetas, Sea el primero en etiquetar este registro!
Descripción
Sumario:The exploration and rational design of easily separable and highly efficient sorbents with satisfactory capability of extracting radioactive uranium (U)-containing compound(s) are of paramount significance. In this study, a novel magnetic hydroxyapatite (HAP) composite (HAP@ CoFe<sub>2</sub>O<sub>4</sub>), which was coupled with cobalt ferrite (CoFe<sub>2</sub>O<sub>4</sub>), was rationally designed for uranium(VI) removal through a facile hydrothermal process. The U(VI) ions were rapidly removed using HAP@ CoFe<sub>2</sub>O<sub>4</sub> within a short time (i.e., 10 min), and a maximum U(VI) removal efficiency of 93.7% was achieved. The maximum adsorption capacity (Q<sub>max</sub>) of the HAP@CoFe<sub>2</sub>O<sub>4</sub> was 338 mg/g, which demonstrated the potential of as-prepared HAP@CoFe<sub>2</sub>O<sub>4</sub> in the purification of U(VI) ions from nuclear effluents. Autunite [Ca(UO<sub>2</sub>)<sub>2</sub>(PO<sub>4</sub>)<sub>2</sub>(H<sub>2</sub>O)<sub>6</sub>] was the main crystalline phase to retain uranium, wherein U(VI) was effectively extracted and immobilized in terms of a relatively stable mineral. Furthermore, the reacted HAP@CoFe<sub>2</sub>O<sub>4</sub> can be magnetically recycled. The results of this study reveal that the suggested process using HAP@CoFe<sub>2</sub>O<sub>4</sub> is a promising approach for the removal and immobilization of U(VI) released from nuclear effluents.