Methodology Development and Determination of Solubility-limiting Solid Phases for a Performance Assessment of Geological Disposal of High-level Radioactive and TRU Wastes

  Evaluation and estimation of solubility values are required for a performance assessment of geological disposal of high-level radioactive and TRU wastes. Selection of solubility-limiting solid phases (SSPs) that control the solubility of radionuclides is necessary for the evaluation and estimation...

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Published inJournal of Nuclear Fuel Cycle and Environment Vol. 27; no. 2; pp. 58 - 71
Main Authors GOTO, Takahiro, SHIBUTANI, Sanae, YOSHIDA, Yasushi, KITAMURA, Akira
Format Journal Article
LanguageEnglish
Published Division of Nuclear Fuel Cycle and Environment, Atomic Energy Society of Japan 15.12.2020
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ISSN1884-7579
1884-7579
DOI10.3327/jnuce.27.2_58

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Abstract   Evaluation and estimation of solubility values are required for a performance assessment of geological disposal of high-level radioactive and TRU wastes. Selection of solubility-limiting solid phases (SSPs) that control the solubility of radionuclides is necessary for the evaluation and estimation of solubility values. The authors have developed a methodology for selection of the SSP through a calculation of saturation indices (SIs) using thermodynamic database to show a transparent procedure for the selection. Literature survey has been performed to confirm decision of the SSP from candidate SSPs which generally have larger SIs from realistic point of view for precipitation and solubility control. The authors have selected the SSPs for the elements of interest for the latest Japanese performance assessment in bentonite and cement porewaters after grouping various water compositions.
AbstractList   Evaluation and estimation of solubility values are required for a performance assessment of geological disposal of high-level radioactive and TRU wastes. Selection of solubility-limiting solid phases (SSPs) that control the solubility of radionuclides is necessary for the evaluation and estimation of solubility values. The authors have developed a methodology for selection of the SSP through a calculation of saturation indices (SIs) using thermodynamic database to show a transparent procedure for the selection. Literature survey has been performed to confirm decision of the SSP from candidate SSPs which generally have larger SIs from realistic point of view for precipitation and solubility control. The authors have selected the SSPs for the elements of interest for the latest Japanese performance assessment in bentonite and cement porewaters after grouping various water compositions.
Author GOTO, Takahiro
YOSHIDA, Yasushi
SHIBUTANI, Sanae
KITAMURA, Akira
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Cites_doi 10.1524/ract.1992.5859.1.71
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10.1080/18811248.2000.9714980
10.1139/v84-070
10.1016/j.apgeochem.2014.12.017
10.1524/ract.1989.48.34.145
10.1524/ract.2002.90.9-11_2002.805
10.1524/ract.1992.56.1.7
10.13182/NT99-A2959
10.1016/0016-7037(84)90051-6
10.1080/00223131.2015.1137245
10.3151/jact.3.77
10.1524/ract.2001.89.1.001
10.1007/s007060170128
10.2343/geochemj.42.295
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– reference: [2] Swedish Nuclear Fuel and Waste Management Co. (SKB): Radionuclide transport and dose calculations for the safety assessment SR-PSU. TR-14-09 (2014).
– reference: [42] Kitamura, A., Kirishima, A., Saito, T., Shibutani, S., Tochiyama, O.: JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes: Selection of thermodynamic data of molybdenum. JAEA-Review 2010-010 (2010) (in Japanese).
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– reference: [21] Berner, U.: Solubility of radionuclides in a bentonite environment for provisional safety analyses for SGT-E2. Technical Report 14-06, Nagra (2014).
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– reference: [29] Berner, U.: Solubility of radionuclides in a concrete environment for provisional safety analyses for SGT-E2. Technical Report 14-07, Nagra (2014).
– reference: [31] Kitamura, A.: Update of JAEA-TDB: Update of thermodynamic data for zirconium and those for isosaccahrinate, tentative selection of thermodynamic data for ternary M2+-UO22+-CO32- system and integration with JAEA’s thermodynamic database for geochemical calculations. JAEA-Data/Code 2018-018, JAEA (2019).
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Snippet   Evaluation and estimation of solubility values are required for a performance assessment of geological disposal of high-level radioactive and TRU wastes....
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SubjectTerms geological disposal
high-level radioactive waste
solubility
solubility-limiting solid phase
thermodynamic database
TRU waste
Title Methodology Development and Determination of Solubility-limiting Solid Phases for a Performance Assessment of Geological Disposal of High-level Radioactive and TRU Wastes
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