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<p>The experimental results showed that 9.13 <i>wt.</i>% of alkali metal of granite, solid solubility limit was 25 <i>wt.</i>%. During the transition to the glassy state and the complete vitrification period, the proportion of Q<sup>3</sup> increased, while the proportions of Q<sup>1</sup> decreased. When exceeding the solid solubility limit, the proportion of Q<sup>3</sup> structure decreased, and the proportions of Q<sup>1</sup> and Q<sup>2</sup> structures increased. Therefore, Q<sup>3</sup> was considered the key part of waste form. In addition, the maximum Vickers hardness was 6.06 GPa and the maximum density was 2.95 g·cm<sup>−3</sup>. After 42 d, the normalized leaching rate of Nd<sup>3+</sup> was 4.01 × 10<sup>–8</sup> g·m<sup>−2</sup>·d<sup>−1</sup>.</p> Graphical Abstract <p></p>

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Encapsulation of simulated nuclear waste Nd2O3 in a granite derived glass–ceramic

  • 期刊论文

  • 发表日期：

    2025年8月5日

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  • Ran Tan,
  • Xiaoyan Shu,
  • Wenhong Han,
  • Jiaqin Wei,
  • Mingfen Wen,
  • Zhanqiang Li,
  • Xirui Lu

摘要

The experimental results showed that 9.13 wt.% of alkali metal of granite, solid solubility limit was 25 wt.%. During the transition to the glassy state and the complete vitrification period, the proportion of Q3 increased, while the proportions of Q1 decreased. When exceeding the solid solubility limit, the proportion of Q3 structure decreased, and the proportions of Q1 and Q2 structures increased. Therefore, Q3 was considered the key part of waste form. In addition, the maximum Vickers hardness was 6.06 GPa and the maximum density was 2.95 g·cm−3. After 42 d, the normalized leaching rate of Nd3+ was 4.01 × 10–8 g·m−2·d−1.

Graphical Abstract