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Immobilization of simulated strontium contaminated zeolite: microstructure and chemical durability

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Abstract

In this study, strontium (Sr) contaminated zeolite was sintered at 1500 °C for 1 h, and the radionuclide was fixed into the glass matrix. The phase evolution, microstructure, morphology, mechanical property, and chemical durability were investigated. The results exhibited that the solid solubility limit of the glass solidified body could reach up to 72 wt%. Compared with other solidified forms of radioactive wastes, the glass matrix synthesized in this study has good mechanical properties and chemical durability. Therefore, high-temperature sintering is a potential method for disposing of the radioactively contaminated zeolite waste.

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Acknowledgements

The authors appreciate the financial support provided by the Research Fund Program of Guangdong Key Laboratory of Radioactive and Rare Resource Utilization (2018B030322009), and the Project of State Key Laboratory of Environment- Friendly Energy Materials, Southwest University of Science and Technology (No. 20FKSY10).

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Authors and Affiliations

  1. State Key Laboratory of Environmental-Friendly Energy Materials, Southwest University of Science and Technology, Mianyang, Sichuan, 621010, People’s Republic of China

    Minghe Shi & Xirui Lu

  2. Fundamental Science On Nuclear Wastes and Environmental Safety Laboratory, Southwest University of Science and Technology, Mianyang, Sichuan, 621010, People’s Republic of China

    Fen Luo, Yulong Miao, Beilong Yuan & Xirui Lu

  3. National Co-Innovation Center for Nuclear Waste Disposal and Environmental Safety, Southwest University of Science and Technology, Mianyang, Sichuan, 621010, People’s Republic of China

    Fen Luo & Xirui Lu

  4. Guangdong Provincial Key Laboratory of Radioactive and Rare Resource Utilization, Shaoguan, Guangdong, 512026, People’s Republic of China

    Zhengfan Xu, Yaping Li & Wenxiao Huang

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  1. Minghe Shi
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  2. Fen Luo
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  3. Yulong Miao
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Shi, M., Luo, F., Miao, Y. et al. Immobilization of simulated strontium contaminated zeolite: microstructure and chemical durability. J Radioanal Nucl Chem 331, 4099–4110 (2022). https://doi.org/10.1007/s10967-022-08465-0

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