Abstract
Natural granite was considered for immobilizing nuclear waste Nd2O3 (Nd3+ simulated for An3+). The structure and performance of pure granite were compared with Nd2O3 doped granite sintered at 1500 °C. The introduced Nd3+ distributed mainly in the glass network below the loading capacity (19 wt.%). Beyond that, tetrahedral SiO4 units existed in a sheet form, while extra Nd3+ precipitated as Nd2Si2O7. The doped Nd2O3 improved the hardness (6.29–7.07 GPa) and density (2.19–2.71 g/cm3) of matrix. Moreover, the solidified form presented NRNd below 1.7 × 10–6 g m−2 d−1 after 28 days. This work disclosed a potential host matrix for nuclear waste.
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Acknowledgements
The authors appreciate the supports from the National Natural Science Foundation of China (No. 21976146), the Project of State Key Laboratory of Environment-friendly Energy Materials, Southwest University of Science and Technology (No. 21fksy13) and the State Environmental Protection Key Laboratory of Synergetic Control and Joint Remediation for Soil & Water Pollution, Chengdu University of Technology (CHBK-2020-005).
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Huang, X., Shu, X., Li, L. et al. Nd2O3 immobilized by granite based glass–ceramics: composition, structure, and performance. J Radioanal Nucl Chem 332, 105–117 (2023). https://doi.org/10.1007/s10967-022-08657-8
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DOI: https://doi.org/10.1007/s10967-022-08657-8