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Technetium Immobilization on Carbon Steel Corrosion Products Under Simulated Geological Radioactive Waste Repository Conditions.

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Title: Technetium Immobilization on Carbon Steel Corrosion Products Under Simulated Geological Radioactive Waste Repository Conditions.
Authors: Abramova, Elena1 (AUTHOR), Artemiev, Grigoriy1 (AUTHOR), German, Konstantin1 (AUTHOR), Safonov, Alexey1 (AUTHOR) alexeysafonof@gmail.com
Source: Materials (1996-1944). Nov2025, Vol. 18 Issue 22, p5220. 19p.
Subjects: Radioactive waste disposal, Geological repositories, Carbon steel corrosion, Bentonite, Radioactive waste management, Oxidizing agents, Anaerobic bacteria, Ferric hydroxides
Geographic Terms: Russia, Krasnoiarskii krai (Russia)
Abstract: The migration of the long-lived isotope technetium-99 (half-life 2.1 × 105 years) presents a significant challenge for the deep geological disposal of radioactive waste. This study investigates the immobilization of technetium by carbon steel corrosion products under aerobic and anaerobic conditions simulating the Yeniseysky site (Krasnoyarsk Region, Russia), a proposed location for a Deep Geological Repository (DGR). Over time, the degradation of barrier materials is expected to allow low-salinity solutions to be brought into contact St3 steel, the intended container material for vitrified radioactive waste in the Russian context, leading to crevice corrosion. The findings demonstrate that carbon steel containers act not merely as a physical barrier but also as a chemical barrier by facilitating the reductive immobilization of technetium. The most effective reduction of technetium was observed in the presence of ferrihydrite as a corrosion product under both aerobic and anaerobic conditions, as indicated by distribution coefficient (Kd) values ranging from 1.4 × 103 to 1.6 × 103 cm3/g. However, the presence of bentonite clay can diminish the efficiency of this process by adsorbing corrosion products, resulting in a 50% reduction in the distribution coefficients. In contrast, leaching products from aluminophosphate glass and cement had a less pronounced effect on technetium immobilization, causing a decrease in distribution coefficients of no more than 30%. The results of this research can be applied to model the long-term behavior of technetium in the evolving environment of a geological radioactive waste repository. [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
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PubTypeId: academicJournal
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  Data: Technetium Immobilization on Carbon Steel Corrosion Products Under Simulated Geological Radioactive Waste Repository Conditions.
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  Data: <searchLink fieldCode="AR" term="%22Abramova%2C+Elena%22">Abramova, Elena</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Artemiev%2C+Grigoriy%22">Artemiev, Grigoriy</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22German%2C+Konstantin%22">German, Konstantin</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Safonov%2C+Alexey%22">Safonov, Alexey</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> alexeysafonof@gmail.com</i>
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  Data: <searchLink fieldCode="JN" term="%22Materials+%281996-1944%29%22">Materials (1996-1944)</searchLink>. Nov2025, Vol. 18 Issue 22, p5220. 19p.
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  Data: <searchLink fieldCode="DE" term="%22Radioactive+waste+disposal%22">Radioactive waste disposal</searchLink><br /><searchLink fieldCode="DE" term="%22Geological+repositories%22">Geological repositories</searchLink><br /><searchLink fieldCode="DE" term="%22Carbon+steel+corrosion%22">Carbon steel corrosion</searchLink><br /><searchLink fieldCode="DE" term="%22Bentonite%22">Bentonite</searchLink><br /><searchLink fieldCode="DE" term="%22Radioactive+waste+management%22">Radioactive waste management</searchLink><br /><searchLink fieldCode="DE" term="%22Oxidizing+agents%22">Oxidizing agents</searchLink><br /><searchLink fieldCode="DE" term="%22Anaerobic+bacteria%22">Anaerobic bacteria</searchLink><br /><searchLink fieldCode="DE" term="%22Ferric+hydroxides%22">Ferric hydroxides</searchLink>
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  Data: <searchLink fieldCode="DE" term="%22Russia%22">Russia</searchLink><br /><searchLink fieldCode="DE" term="%22Krasnoiarskii+krai+%28Russia%29%22">Krasnoiarskii krai (Russia)</searchLink>
– Name: Abstract
  Label: Abstract
  Group: Ab
  Data: The migration of the long-lived isotope technetium-99 (half-life 2.1 × 105 years) presents a significant challenge for the deep geological disposal of radioactive waste. This study investigates the immobilization of technetium by carbon steel corrosion products under aerobic and anaerobic conditions simulating the Yeniseysky site (Krasnoyarsk Region, Russia), a proposed location for a Deep Geological Repository (DGR). Over time, the degradation of barrier materials is expected to allow low-salinity solutions to be brought into contact St3 steel, the intended container material for vitrified radioactive waste in the Russian context, leading to crevice corrosion. The findings demonstrate that carbon steel containers act not merely as a physical barrier but also as a chemical barrier by facilitating the reductive immobilization of technetium. The most effective reduction of technetium was observed in the presence of ferrihydrite as a corrosion product under both aerobic and anaerobic conditions, as indicated by distribution coefficient (Kd) values ranging from 1.4 × 103 to 1.6 × 103 cm3/g. However, the presence of bentonite clay can diminish the efficiency of this process by adsorbing corrosion products, resulting in a 50% reduction in the distribution coefficients. In contrast, leaching products from aluminophosphate glass and cement had a less pronounced effect on technetium immobilization, causing a decrease in distribution coefficients of no more than 30%. The results of this research can be applied to model the long-term behavior of technetium in the evolving environment of a geological radioactive waste repository. [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/ma18225220
    Languages:
      – Code: eng
        Text: English
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      Pagination:
        PageCount: 19
        StartPage: 5220
    Subjects:
      – SubjectFull: Radioactive waste disposal
        Type: general
      – SubjectFull: Geological repositories
        Type: general
      – SubjectFull: Carbon steel corrosion
        Type: general
      – SubjectFull: Bentonite
        Type: general
      – SubjectFull: Radioactive waste management
        Type: general
      – SubjectFull: Oxidizing agents
        Type: general
      – SubjectFull: Anaerobic bacteria
        Type: general
      – SubjectFull: Ferric hydroxides
        Type: general
      – SubjectFull: Russia
        Type: general
      – SubjectFull: Krasnoiarskii krai (Russia)
        Type: general
    Titles:
      – TitleFull: Technetium Immobilization on Carbon Steel Corrosion Products Under Simulated Geological Radioactive Waste Repository Conditions.
        Type: main
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          Name:
            NameFull: Abramova, Elena
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            NameFull: Artemiev, Grigoriy
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            NameFull: German, Konstantin
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            NameFull: Safonov, Alexey
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            – D: 15
              M: 11
              Text: Nov2025
              Type: published
              Y: 2025
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              Value: 19961944
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              Value: 18
            – Type: issue
              Value: 22
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            – TitleFull: Materials (1996-1944)
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