Modelling of chemical evolution in the near-field of the spent nuclear fuel repository: A case study

Heikki Kumpulainen, Jarmo Lehikoinen, Arto Muurinen

    Research output: Book/ReportReport

    Abstract

    It has been planned to dispose of spent nuclear fuel in Finland in a repository at a depth of about 500 m in crystalline bedrock. The near-field barriers in the excavated space comprise a compacted bentonite buffer (clay) surrounding a copper-lined iron canister, the canister itself and the spent fuel matrix (UO2). The barriers mutually interact via the groundwater and tend towards a thermodynamic equilibrium with each other and the geochemical environment. The evolution of the near-field chemistry arising from the interactions between the groundwater, bentonite, canister and the spent fuel was calculated for the groundwater and bentonite composition considered in the context of the Finnish nuclear waste disposal concept. The approach employs equilibrium modelling (EQ3/6) with the modelling of three successive closed systems. The pH, Eh and actinide solubilities as well as their solubility-limiting phases were determined in the solution equilibrated with spent fuel.
    Original languageEnglish
    Place of PublicationEspoo
    PublisherVTT Technical Research Centre of Finland
    Number of pages24
    ISBN (Print)951-38-5611-9
    Publication statusPublished - 1999
    MoE publication typeNot Eligible

    Publication series

    SeriesVTT Tiedotteita - Meddelanden - Research Notes
    Number2000
    ISSN1235-0605

    Fingerprint

    bentonite
    repository
    groundwater
    solubility
    modeling
    actinide
    waste disposal
    radioactive waste
    bedrock
    thermodynamics
    copper
    iron
    clay
    matrix
    chemical
    nuclear fuel

    Keywords

    • nuclear fuels
    • spent fuels
    • radioactive wastes
    • waste disposal
    • repositories
    • ground water
    • bentonite
    • reactions
    • modelling

    Cite this

    Kumpulainen, H., Lehikoinen, J., & Muurinen, A. (1999). Modelling of chemical evolution in the near-field of the spent nuclear fuel repository: A case study. Espoo: VTT Technical Research Centre of Finland. VTT Tiedotteita - Meddelanden - Research Notes, No. 2000
    Kumpulainen, Heikki ; Lehikoinen, Jarmo ; Muurinen, Arto. / Modelling of chemical evolution in the near-field of the spent nuclear fuel repository : A case study. Espoo : VTT Technical Research Centre of Finland, 1999. 24 p. (VTT Tiedotteita - Meddelanden - Research Notes; No. 2000).
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    abstract = "It has been planned to dispose of spent nuclear fuel in Finland in a repository at a depth of about 500 m in crystalline bedrock. The near-field barriers in the excavated space comprise a compacted bentonite buffer (clay) surrounding a copper-lined iron canister, the canister itself and the spent fuel matrix (UO2). The barriers mutually interact via the groundwater and tend towards a thermodynamic equilibrium with each other and the geochemical environment. The evolution of the near-field chemistry arising from the interactions between the groundwater, bentonite, canister and the spent fuel was calculated for the groundwater and bentonite composition considered in the context of the Finnish nuclear waste disposal concept. The approach employs equilibrium modelling (EQ3/6) with the modelling of three successive closed systems. The pH, Eh and actinide solubilities as well as their solubility-limiting phases were determined in the solution equilibrated with spent fuel.",
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    Kumpulainen, H, Lehikoinen, J & Muurinen, A 1999, Modelling of chemical evolution in the near-field of the spent nuclear fuel repository: A case study. VTT Tiedotteita - Meddelanden - Research Notes, no. 2000, VTT Technical Research Centre of Finland, Espoo.

    Modelling of chemical evolution in the near-field of the spent nuclear fuel repository : A case study. / Kumpulainen, Heikki; Lehikoinen, Jarmo; Muurinen, Arto.

    Espoo : VTT Technical Research Centre of Finland, 1999. 24 p. (VTT Tiedotteita - Meddelanden - Research Notes; No. 2000).

    Research output: Book/ReportReport

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    N2 - It has been planned to dispose of spent nuclear fuel in Finland in a repository at a depth of about 500 m in crystalline bedrock. The near-field barriers in the excavated space comprise a compacted bentonite buffer (clay) surrounding a copper-lined iron canister, the canister itself and the spent fuel matrix (UO2). The barriers mutually interact via the groundwater and tend towards a thermodynamic equilibrium with each other and the geochemical environment. The evolution of the near-field chemistry arising from the interactions between the groundwater, bentonite, canister and the spent fuel was calculated for the groundwater and bentonite composition considered in the context of the Finnish nuclear waste disposal concept. The approach employs equilibrium modelling (EQ3/6) with the modelling of three successive closed systems. The pH, Eh and actinide solubilities as well as their solubility-limiting phases were determined in the solution equilibrated with spent fuel.

    AB - It has been planned to dispose of spent nuclear fuel in Finland in a repository at a depth of about 500 m in crystalline bedrock. The near-field barriers in the excavated space comprise a compacted bentonite buffer (clay) surrounding a copper-lined iron canister, the canister itself and the spent fuel matrix (UO2). The barriers mutually interact via the groundwater and tend towards a thermodynamic equilibrium with each other and the geochemical environment. The evolution of the near-field chemistry arising from the interactions between the groundwater, bentonite, canister and the spent fuel was calculated for the groundwater and bentonite composition considered in the context of the Finnish nuclear waste disposal concept. The approach employs equilibrium modelling (EQ3/6) with the modelling of three successive closed systems. The pH, Eh and actinide solubilities as well as their solubility-limiting phases were determined in the solution equilibrated with spent fuel.

    KW - nuclear fuels

    KW - spent fuels

    KW - radioactive wastes

    KW - waste disposal

    KW - repositories

    KW - ground water

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    KW - reactions

    KW - modelling

    M3 - Report

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    Kumpulainen H, Lehikoinen J, Muurinen A. Modelling of chemical evolution in the near-field of the spent nuclear fuel repository: A case study. Espoo: VTT Technical Research Centre of Finland, 1999. 24 p. (VTT Tiedotteita - Meddelanden - Research Notes; No. 2000).