Influence of Simulated Radioactive Waste Resins on the Properties of Magnesium Silicate Hydrate Cement.
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| Title: | Influence of Simulated Radioactive Waste Resins on the Properties of Magnesium Silicate Hydrate Cement. |
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| Authors: | Sun, Enyu1 (AUTHOR), Gao, Huinan2 (AUTHOR), Li, Min3,4 (AUTHOR), Yang, Jie4,5 (AUTHOR), Qiao, Yu4,5,6 (AUTHOR), Zhang, Tingting4,6 (AUTHOR) |
| Source: | Materials (1996-1944). Dec2025, Vol. 18 Issue 23, p5385. 21p. |
| Subjects: | Ion exchange resins, Radioactive wastes, Durability, Mechanical behavior of materials, Magnesium silicates, Hydration, Leaching, Solidification |
| Abstract: | Ion exchange resins are commonly utilized for treating liquid radioactive waste within nuclear power plants; however, the disposal of these waste resins presents a new challenge. In this study, magnesium silicate hydrate cement (MSHC) was used to immobilize the waste resin, and the immobilization effectiveness of the MSHC-solidified body were assessed by mechanical properties, durability, and leaching performance. Hydration heat, X-ray diffraction (XRD), thermogravimetric analysis (TGA), scanning electronic microscopy (SEM), and mercury intrusion porosimetry (MIP) were used to study the hydration process of the MSHC-solidified body containing Cs+, Sr2+, and Cs+/Sr2+ waste resins. The results demonstrated that the presence of waste resins slightly delayed the hydration reaction process of MSHC and reduced the polymerization degree of the M-S-H gel, and the composition of the hydration products were not changed. The immobilization mechanism for radionuclide ions in resin included both mechanical encapsulation and surface adsorption, and the leaching of Cs+ and Sr2+ from MSHC-solidified body followed the FRDIM. When the content of the waste resin was 25%, the MSHC-solidified body exhibited satisfactory compressive strength, freeze-thaw resistance, soaking resistance, and impact resistance. These results strongly indicated that MSHC possessed the ability to effectively immobilize ion exchange resins. [ABSTRACT FROM AUTHOR] |
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| Database: | Engineering Source |
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| Abstract: | Ion exchange resins are commonly utilized for treating liquid radioactive waste within nuclear power plants; however, the disposal of these waste resins presents a new challenge. In this study, magnesium silicate hydrate cement (MSHC) was used to immobilize the waste resin, and the immobilization effectiveness of the MSHC-solidified body were assessed by mechanical properties, durability, and leaching performance. Hydration heat, X-ray diffraction (XRD), thermogravimetric analysis (TGA), scanning electronic microscopy (SEM), and mercury intrusion porosimetry (MIP) were used to study the hydration process of the MSHC-solidified body containing Cs+, Sr2+, and Cs+/Sr2+ waste resins. The results demonstrated that the presence of waste resins slightly delayed the hydration reaction process of MSHC and reduced the polymerization degree of the M-S-H gel, and the composition of the hydration products were not changed. The immobilization mechanism for radionuclide ions in resin included both mechanical encapsulation and surface adsorption, and the leaching of Cs+ and Sr2+ from MSHC-solidified body followed the FRDIM. When the content of the waste resin was 25%, the MSHC-solidified body exhibited satisfactory compressive strength, freeze-thaw resistance, soaking resistance, and impact resistance. These results strongly indicated that MSHC possessed the ability to effectively immobilize ion exchange resins. [ABSTRACT FROM AUTHOR] |
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| ISSN: | 19961944 |
| DOI: | 10.3390/ma18235385 |
