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<p>In this study, borosilicate glasses with different ZrO<sub>2</sub> contents were synthesized at 1200 °C and used to immobilize simulated TRPO waste. The effects of ZrO<sub>2</sub> content on the solid solution limit, microstructure, mechanical properties, and chemical stability of the solidified bodies were systematically analyzed. The results showed that with the increase of ZrO<sub>2</sub> content, the solid solution limit of TRPO waste increased from 20 to 30 wt%, and the degree of amorphization of the solidified bodies could be improved. The addition of ZrO<sub>2</sub> raised the number of bridging oxygen bonds in the solidified body and enhanced the degree of polymerization of the glass structure. For samples containing 4 wt% ZrO<sub>2</sub>, the highest Vickers hardness and density values were 6.57 GPa and 2.89&#xa0;g&#xa0;cm<sup>−3</sup>. Moreover, the 42-day normalized leaching rates of Ce, Nd, La, and Pr in the solidified bodies were about 10<sup>−5</sup>&#xa0;g&#xa0;m<sup>−2</sup>&#xa0;d<sup>−1</sup>. This work provides useful ideas for the optimization of the solidification matrix materials for high-level radioactive waste.</p> Graphical abstract <p></p>

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The influence of ZrO2 on borosilicate glass solidification of TRPO wastes: microstructure and chemical stability

  • 期刊论文

  • 发表日期：

    2025年10月14日

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  • Yu Gao,
  • Fen Luo,
  • Yang Li,
  • Shangqi Yang,
  • Xirui Lu

摘要

In this study, borosilicate glasses with different ZrO2 contents were synthesized at 1200 °C and used to immobilize simulated TRPO waste. The effects of ZrO2 content on the solid solution limit, microstructure, mechanical properties, and chemical stability of the solidified bodies were systematically analyzed. The results showed that with the increase of ZrO2 content, the solid solution limit of TRPO waste increased from 20 to 30 wt%, and the degree of amorphization of the solidified bodies could be improved. The addition of ZrO2 raised the number of bridging oxygen bonds in the solidified body and enhanced the degree of polymerization of the glass structure. For samples containing 4 wt% ZrO2, the highest Vickers hardness and density values were 6.57 GPa and 2.89 g cm−3. Moreover, the 42-day normalized leaching rates of Ce, Nd, La, and Pr in the solidified bodies were about 10−5 g m−2 d−1. This work provides useful ideas for the optimization of the solidification matrix materials for high-level radioactive waste.

Graphical abstract