Structure and Properties of Uranium‐Containing ZrSiO <sub>4</sub> Microcrystalline Glasses: Intriguing Electron Adjustment

ABSTRACT Radioactive spent silica gel is a type of secondary waste generated during the decontamination and purification processes of spent fuel reprocessing. This work reports borosilicate glass containing zircon mineral phases to achieve the immobilization of such waste. The physical phase evolution, microstructure, and immobilization mechanism were systematically investigated. The XRD and refinement results confirmed the lattice substitution of uranium in zircon crystals. The XPS and UV‐vis‐DRS results demonstrated that the uranium mainly showed quadrivalent and pentavalent states in the ZrSiO 4 crystal. The FT‐IR results demonstrated that the microcrystal glass became more structurally intact and polymerized as the uranium content in the crystal increased. EPR analysis and theoretical calculations revealed that the entry of uranium into the ZrSiO 4 structure adjusted the amount of oxygen vacancy defects in the material. The electron density difference analysis showed that the electrons produced by the vacancy defects were concentrated on the surrounding oxygen atoms. Ultimately, these behaviors enhanced the chemical stability of the material. This work provides a good strategy for the disposal of this waste and a new perspective on the entry of uranium atoms into the zircon structure in the field of radioactive waste disposal.

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Journal
Journal of the American Ceramic Society
Published
2026-03-24
DOI
https://doi.org/10.1111/jace.70617
Primary Topic
Nuclear materials and radiation effects
Type
article
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article

Structure and Properties of Uranium‐Containing ZrSiO 4 Microcrystalline Glasses: Intriguing Electron Adjustment

Wencai Cheng, Congcong Ding, Zhen-Wei Niu, Xiaoyan Shu et al.
Journal of the American Ceramic Society
Nuclear materials and radiation effects
article

Structure and Properties of Uranium‐Containing ZrSiO 4 Microcrystalline Glasses: Intriguing Electron Adjustment

Wencai Cheng, Congcong Ding, Zhen-Wei Niu, Xiaoyan Shu, Xirui Lu, Ze Qiu, Dong Wu
article en

Abstract

ABSTRACT Radioactive spent silica gel is a type of secondary waste generated during the decontamination and purification processes of spent fuel reprocessing. This work reports borosilicate glass containing zircon mineral phases to achieve the immobilization of such waste. The physical phase evolution, microstructure, and immobilization mechanism were systematically investigated. The XRD and refinement results confirmed the lattice substitution of uranium in zircon crystals. The XPS and UV‐vis‐DRS results demonstrated that the uranium mainly showed quadrivalent and pentavalent states in the ZrSiO 4 crystal. The FT‐IR results demonstrated that the microcrystal glass became more structurally intact and polymerized as the uranium content in the crystal increased. EPR analysis and theoretical calculations revealed that the entry of uranium into the ZrSiO 4 structure adjusted the amount of oxygen vacancy defects in the material. The electron density difference analysis showed that the electrons produced by the vacancy defects were concentrated on the surrounding oxygen atoms. Ultimately, these behaviors enhanced the chemical stability of the material. This work provides a good strategy for the disposal of this waste and a new perspective on the entry of uranium atoms into the zircon structure in the field of radioactive waste disposal.

Journal of the American Ceramic SocietyVol. 109(4)
University of Science and Technology of China (CN), Southwest University of Science and Technology (CN), Southwest Petroleum University (CN), Artificial Intelligence in Medicine (Canada) (CA)
Openalex Percentile: Top 11%
Nuclear materials and radiation effects
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