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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.
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]
Copyright of Materials (1996-1944) is the property of MDPI and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
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DbLabel: Engineering Source
An: 190517534
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PubTypeId: academicJournal
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  Label: Title
  Group: Ti
  Data: Influence of Simulated Radioactive Waste Resins on the Properties of Magnesium Silicate Hydrate Cement.
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  Data: <searchLink fieldCode="AR" term="%22Sun%2C+Enyu%22">Sun, Enyu</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Gao%2C+Huinan%22">Gao, Huinan</searchLink><relatesTo>2</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Li%2C+Min%22">Li, Min</searchLink><relatesTo>3,4</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Yang%2C+Jie%22">Yang, Jie</searchLink><relatesTo>4,5</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Qiao%2C+Yu%22">Qiao, Yu</searchLink><relatesTo>4,5,6</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Zhang%2C+Tingting%22">Zhang, Tingting</searchLink><relatesTo>4,6</relatesTo> (AUTHOR)
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  Data: <searchLink fieldCode="JN" term="%22Materials+%281996-1944%29%22">Materials (1996-1944)</searchLink>. Dec2025, Vol. 18 Issue 23, p5385. 21p.
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  Data: <searchLink fieldCode="DE" term="%22Ion+exchange+resins%22">Ion exchange resins</searchLink><br /><searchLink fieldCode="DE" term="%22Radioactive+wastes%22">Radioactive wastes</searchLink><br /><searchLink fieldCode="DE" term="%22Durability%22">Durability</searchLink><br /><searchLink fieldCode="DE" term="%22Mechanical+behavior+of+materials%22">Mechanical behavior of materials</searchLink><br /><searchLink fieldCode="DE" term="%22Magnesium+silicates%22">Magnesium silicates</searchLink><br /><searchLink fieldCode="DE" term="%22Hydration%22">Hydration</searchLink><br /><searchLink fieldCode="DE" term="%22Leaching%22">Leaching</searchLink><br /><searchLink fieldCode="DE" term="%22Solidification%22">Solidification</searchLink>
– Name: Abstract
  Label: Abstract
  Group: Ab
  Data: 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]
– Name: AbstractSuppliedCopyright
  Label:
  Group: Ab
  Data: <i>Copyright of Materials (1996-1944) is the property of MDPI and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.)
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RecordInfo BibRecord:
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    Identifiers:
      – Type: doi
        Value: 10.3390/ma18235385
    Languages:
      – Code: eng
        Text: English
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      Pagination:
        PageCount: 21
        StartPage: 5385
    Subjects:
      – SubjectFull: Ion exchange resins
        Type: general
      – SubjectFull: Radioactive wastes
        Type: general
      – SubjectFull: Durability
        Type: general
      – SubjectFull: Mechanical behavior of materials
        Type: general
      – SubjectFull: Magnesium silicates
        Type: general
      – SubjectFull: Hydration
        Type: general
      – SubjectFull: Leaching
        Type: general
      – SubjectFull: Solidification
        Type: general
    Titles:
      – TitleFull: Influence of Simulated Radioactive Waste Resins on the Properties of Magnesium Silicate Hydrate Cement.
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          Name:
            NameFull: Sun, Enyu
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            NameFull: Gao, Huinan
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            NameFull: Li, Min
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            NameFull: Yang, Jie
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            NameFull: Qiao, Yu
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            – D: 01
              M: 12
              Text: Dec2025
              Type: published
              Y: 2025
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              Value: 18
            – Type: issue
              Value: 23
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