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 in | Journal of Nuclear Fuel Cycle and Environment Vol. 27; no. 2; pp. 58 - 71 |
|---|---|
| Main Authors | , , , |
| Format | Journal Article |
| Language | English |
| Published |
Division of Nuclear Fuel Cycle and Environment, Atomic Energy Society of Japan
15.12.2020
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| Subjects | |
| Online Access | Get full text |
| ISSN | 1884-7579 1884-7579 |
| DOI | 10.3327/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. |
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| 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 |
| Author_xml | – sequence: 1 fullname: GOTO, Takahiro organization: Nuclear Waste Management Organization of Japan – sequence: 1 fullname: SHIBUTANI, Sanae organization: Nuclear Waste Management Organization of Japan – sequence: 1 fullname: YOSHIDA, Yasushi organization: NESI Company Limited – sequence: 1 fullname: KITAMURA, Akira organization: Japan Atomic Energy Agency |
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| CitedBy_id | crossref_primary_10_3208_jgs_19_273 crossref_primary_10_1080_00223131_2021_1936255 |
| Cites_doi | 10.1524/ract.1992.5859.1.71 10.1007/BF00649561 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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[52] Kitamura, A., Fujiwara, K., Yui, M.: JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes: Refinement of thermodynamic data for trivalent actinoids and samarium. JAEA-Review 2009-047, JAEA (2010). [5] Lemire, R., Berner, U., Musikas, C., Palmer, D. A., Taylor, P., Tochiyama, O.:Chemical Thermodynamics of Iron (Part 1). OECD, Paris (2013). [24] Nuclear Waste Management Organization of Canada (NWMO): Pre-project report on adaptive phased management - Used fuel repository conceptual design and postclosure safety assessment in crystalline rock. TR-2012-16 (2012). [30] Kitamura, A., Fujiwara, K., Doi, R., Yoshida Y., Mihara, M., Terashima, M., Yui, M.: JAEA thermodynamic database for performance assessment of geological disposal of high-level radioactive and TRU wastes. JAEA-Data/Code 2009-024, JAEA (2010). [36] Hirao, H., Yamada, K., Takahashi, H., Zibara, H.: Chloride binding of cement estimated by binding isotherms of hydrates. 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| References_xml | – reference: [17] Wersin, P., Kiczka, M., Rosch, D.: Safety case for the disposal of spent nuclear fuel at Olkiluoto - Radionuclide solubility limits and migration parameters for the canister and buffer. POSIVA 2012-39, Posiva Oy (2014). – reference: [35] Parkhurst, D. L., Appelo, C. A. J.: Description of input and examples for PHREEQC version 3 - A computer program for speciation, batch-reaction, one-dimensional transport, and inverse geochemical calculations. U. S. Geological Survey Techniques and Methods, Book 6, Chap. A43, 497 p. (2013). – reference: [5] Lemire, R., Berner, U., Musikas, C., Palmer, D. A., Taylor, P., Tochiyama, O.:Chemical Thermodynamics of Iron (Part 1). OECD, Paris (2013). – 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). – reference: [43] Felmy, A. R., Rai, D., Mason, M. J.: The solubility of CaMoO4(c) and an aqueous thermodynamic model for Ca2+-MoO42--ion-interactions. J. Solution Chem. 21, pp.525-532 (1992). – reference: [21] Berner, U.: Solubility of radionuclides in a bentonite environment for provisional safety analyses for SGT-E2. Technical Report 14-06, Nagra (2014). – reference: [18] Curti, E., Wersin, P.: Assessment of porewater chemistry in the bentonite backfill for the Swiss SF/HLW repository. Technical Report 02-09, Nagra (2002). – 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). – reference: [12] Rand, M., Fuger, J., Grenthe, I., Neck, V., Rai, D.: Chemical Thermodynamics of Thorium. Elsevier, Amsterdam (2008). – reference: [19] Berner, U.: Project Opalinus Clay - Radionuclide concentration limits in the near-field of a repository for spent fuel and vitrified high-level waste. Technical Report 02-10, Nagra (2002). – reference: [27] Berner, U.: Project Opalinus Clay - Radionuclide concentration limits in the cementitious near-field of an ILW repository . Technical Report 02-22, Nagra (2002). – reference: [30] Kitamura, A., Fujiwara, K., Doi, R., Yoshida Y., Mihara, M., Terashima, M., Yui, M.: JAEA thermodynamic database for performance assessment of geological disposal of high-level radioactive and TRU wastes. JAEA-Data/Code 2009-024, JAEA (2010). – reference: [49] Toyohara, M., Kaneko, M., Ueda, H., Mitsutsuka, N., Fujihara, H., Murase, T., Saito N.: Iodine sorption onto mixed solid alumina cement and calcium compounds. J. Nucl. Sci. Technol. 37(11), pp.970-978 (2000). – reference: [53] Rai, D., Felmy, A. R., Fulton, R. W.: Solubility and ion activity product of AmPO4·xH2O(am). Radiochim. Acta 56(1), pp.7-14 (1992). – reference: [26] JAEA Radioactive Waste Processing and Disposal Research Department: Preliminary assessment of geological disposal system for spent fuel in Japan - First progress report on direct disposal -. JAEA-Research 2015-016 (2015) (in Japanese). – reference: [9] Brown, P. L., Curti, E., Grambow, B., Ekberg, C.: Chemical Thermodynamics of Zirconium. Elsevier, Amsterdam (2005). – reference: [46] Rard, J. A., Rand, M. H., Anderegg, G., Wanner, H.: Chemical Thermodynamics of Technetium. Elsevier, Amsterdam (1999). – reference: [6] Lemire, R. J., Palmer, D. A., Taylor, P., Schlenz, H.: Chemical Thermodynamics of Iron (Part 2) . OECD, Paris (2013). – reference: [36] Hirao, H., Yamada, K., Takahashi, H., Zibara, H.: Chloride binding of cement estimated by binding isotherms of hydrates. J. Adv. Concrete Technol.3(1), pp.77-84 (2005). – reference: [51] Taylor, P., Lopata, V. J.: Stability and solubility relationships between some solids in the system PbO-CO2-H2O. Can. J. Chem. 62, pp.395-402 (1984). – reference: [15] Grivé, M., Domènech, C., Montoya, V., García, D., Duro, L.: Determination and assessment of the concentration limits to be used in SR-Can - Supplement to TR-06-32. R-10-50, SKB (2010). – reference: [50] Uhler, A. D., Helz, G. R.: Solubility product of galena at 298 °K: A possible explanation for apparent supersaturation in nature. Geochim. Cosmochim. Acta 48, pp.1155-1160 (1984). – reference: [45] Morin, K. A., Hutt, N. M.: Geochemical characterization of molybdenum leaching from rock and tailings at the Brenda Minesite, British Columbia. Proceedings of the 1999 Workshop on Molybdenum Issues in Reclamation (Price, W. A., Hart, B., and Howell, C. ed.) Kamloops, U.S.A., September 24, 1999, pp.76-85 (1999). – reference: [41] Talerico, C., Ochs, M., Giffaut, E.: Solubility of Nb(V) under cementitious conditions: Importance of Ca-niobate. Scientific Basis for Nuclear Waste Management XXVIII(Mat. Res. Soc. Symp. Proc Vol. 824), (Hanchar, J. M., Stroes-Gascoyne, S., and Browning, L. ed.) San Francisco, U.S.A., April 13-16, 2004, CC8.31 (6 p.) 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Geochem.55, pp.85-94 (2015). – reference: [1] Nuclear Energy Agency (NEA) within Organisation for Economic Co-Operation and Development (OECD): Geologic Disposal of Radioactive Waste in Perspective. OECD, Paris (2000). – reference: [22] National Agency for Radioactive Waste Management (ANDRA): Dossier 2005 Argile - Tome: Phenomenological evolution of a geological repository. ANDRA (2005). – reference: [37] Thoenen, T.: Pitfalls in the use of solubility limits for radioactive waste disposal: The case of nickel in sulfidic groundwaters. Nucl. Technol.126(1), pp.75-87 (1999). – reference: [52] Kitamura, A., Fujiwara, K., Yui, M.: JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes: Refinement of thermodynamic data for trivalent actinoids and samarium. JAEA-Review 2009-047, JAEA (2010). – reference: [57] U. S. Department of Energy (US-DOE): Yucca Mountain repository license application: Safety analysis report. 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| 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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