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<p>The safe disposal of radioactive sludge generated from the use of nuclear energy is crucial. In this study, the simulated radioactive sludge was successfully vitrified via microwave sintering with the addition of NH<sub>4</sub>H<sub>2</sub>PO<sub>4</sub>, forming Na<sub>2</sub>O-Al<sub>2</sub>O<sub>3</sub>-Fe<sub>2</sub>O<sub>3</sub>-P<sub>2</sub>O<sub>5</sub> (SAIP) system glass, and monazite glass–ceramic was simultaneously produced. The phase evolution, microstructure, density, and chemical stability of the sintered samples were systematically researched. The results indicated that vitrification of the sintered samples can be achieved when the NH<sub>4</sub>H<sub>2</sub>PO<sub>4</sub> content in the radioactive sludge reaches 65 <i>wt</i>.% at temperatures of 1200&#xa0;°C and 1300&#xa0;°C. The maximum solid solubility level of Nd in the glass structure was 45 <i>wt</i>.% at 1200&#xa0;°C and 46 <i>wt</i>.% at 1300&#xa0;°C. Moreover, the density of the sintered samples ranged from 2.62 to 3.12&#xa0;g/cm<sup>3</sup>, and they exhibited excellent leaching resistance. The results of this study provide a new perspective for the safe disposal of radioactive sludge.</p>

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Phosphate-based glasses and glass–ceramics for immobilization of simulated radioactive sludge via microwave sintering: mechanism and performance

  • 期刊论文

  • 发表日期：

    2025年1月23日

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  • Kun Huang,
  • Gaiyuan Chen,
  • Xiangyang Li,
  • Yupeng Xie,
  • Yong Liu,
  • Yang Yang,
  • Yuzhen Mai,
  • Keyou Shi

摘要

The safe disposal of radioactive sludge generated from the use of nuclear energy is crucial. In this study, the simulated radioactive sludge was successfully vitrified via microwave sintering with the addition of NH4H2PO4, forming Na2O-Al2O3-Fe2O3-P2O5 (SAIP) system glass, and monazite glass–ceramic was simultaneously produced. The phase evolution, microstructure, density, and chemical stability of the sintered samples were systematically researched. The results indicated that vitrification of the sintered samples can be achieved when the NH4H2PO4 content in the radioactive sludge reaches 65 wt.% at temperatures of 1200 °C and 1300 °C. The maximum solid solubility level of Nd in the glass structure was 45 wt.% at 1200 °C and 46 wt.% at 1300 °C. Moreover, the density of the sintered samples ranged from 2.62 to 3.12 g/cm3, and they exhibited excellent leaching resistance. The results of this study provide a new perspective for the safe disposal of radioactive sludge.