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<p>Uranium tailings were employed as a precursor for glass–ceramic immobilization of La<sup>3+</sup>. The effects of tailings content and sintering temperature on phase evolution and durability were investigated. The results indicated that the U20 (20&#xa0;wt.% uranium tailing addition) samples sintered at 1300&#xa0;°C were an ideal waste form to immobilize La<sup>3+</sup>, with 69.95&#xa0;wt.% of La<sup>3+</sup> incorporated in the NaLa<sub>9</sub>(SiO<sub>4</sub>)<sub>6</sub>O<sub>2</sub> crystalline phase, and an excellent chemical durability (LR<sub>La</sub> = 1.89 × 10<sup>–5</sup>&#xa0;g&#xa0;m<sup>−2</sup> d<sup>−1</sup> after 28&#xa0;days leaching period). This study demonstrated that uranium tailings-based glass–ceramics had a good structural and chemical durability, offering a potential host matrix for radioactive waste and mining byproducts.</p>

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Distribution and leaching characteristics of La element in oxyapatite glass–ceramic derived from uranium tailings

  • 期刊论文

  • 发表日期：

    2026年1月1日

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  • Pingping Huang,
  • Mingfeng Chen,
  • Jiajun Wang,
  • Wanrong Zou,
  • Zhitao Hu

摘要

Uranium tailings were employed as a precursor for glass–ceramic immobilization of La3+. The effects of tailings content and sintering temperature on phase evolution and durability were investigated. The results indicated that the U20 (20 wt.% uranium tailing addition) samples sintered at 1300 °C were an ideal waste form to immobilize La3+, with 69.95 wt.% of La3+ incorporated in the NaLa9(SiO4)6O2 crystalline phase, and an excellent chemical durability (LRLa = 1.89 × 10–5 g m−2 d−1 after 28 days leaching period). This study demonstrated that uranium tailings-based glass–ceramics had a good structural and chemical durability, offering a potential host matrix for radioactive waste and mining byproducts.