Abstract
The quantity of radioactive waste will grow significantly with an increasing interest and use of nuclear-generated energy. There will always be inevitable radioactive waste residues that require disposal, even using an advanced nuclear fuel cycle in the future. Deep geological disposal, one of the most promising final disposal methods, should be validated for its long-term performance and safety assessment. Geotechnical issues related to the deep geological disposal are critical for the sustainable development of nuclear energy. They play challenging roles especially under extreme circumstances that result from deep geological conditions of a repository, extremely long containment time, and the characteristics of nuclear waste itself such as high decay heat, which may primarily affect thermo-hydro-mechanical and geochemical-coupled behavior of a repository for geologic time scales. This paper introduces an overview of deep geological disposal concepts based on Finnish, Korean, Spanish, and Swedish disposal programs, discusses the outstanding research issues in disposal from the aspect of geological and geotechnical engineering, such as Excavation-Damaged Zone (EDZ), cementitious material, long-term gas migration, and self-sealing/healing of fractured rocks with a focus on the state of the art in-situ validation experiments, and additionally presents a numerical modeling of the coupled THMG process in the repository near field, which is one of the major factors concerning the fuel canisters.
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Alexander, W. R. and Mckinley, L. E. (2007). Deep geological disposal of radioactive waste, Radioactivity in the Environment Vol. 9, Elsevier, Oxford.
Alonso, E., Gens, A., and Josa, A. (1990). “A constitutive model for partially saturated soils.” Géotechnique, Vol. 40, No. 3, pp. 405–430.
Andersson, C. G., Emilsson, G., Eriksson, P., and Westman, M. (2004). Status report, canister fabrication, SKB TR-04-23, Swedish Nuclear Fuel and Waste Manangement Co., Stockholm.
Autio, J. and Kirkkomäki, T. (1996). Boring of full scale demonstration holes using a novel dry blind boring method, SKB TR-96-21, Swedish Nuclear Fuel and Waste Manangement Co., Stockholm.
Bäckblom, G. and Lindgren, E. (2005). KBS-3H-Excavation of two horizontal drifts at the Äspö Hard Rock Laboratory during year 2004–2005, SKB R-05-44, Swedish Nuclear Fuel and Waste Manangement Co., Stockholm.
Bastiaens, W., Bernier, F., and Li, X. L. (2007). “SELFRAC: Experiments and conclusions on fracturing, self-healing and self-sealing processes in clays.” Physics and Chemistry of the Earth, Vol. 32, Nos. 8–14, pp. 600–615.
Bernier, F., Li, X. L., Bastiaens, W., Ortiz, L., Van Geet M., Wouters, L., Frieg, B., Blümling, P., Desrues, J., Viaggiani, G. Coll, C., Chanchole, S., De Greef, V., Hamza, R., Malinsky, L., Vervoort, A., Vanbrabant, Y., Debecker, B., Verstraelen, J., Govaerts, A., Wevers, M., Labiouse, V., Escoffier, S., Mathier, J. F., Gastaldo, L., Bühler, (2007). Fractures and self-healing within the excavation disturbed zone in clays (SELFRAC), SELFRAC Project Final Report, European Commission.
Bodansky, D. (2004). Nuclear energy: Principles, practices and prospects, 2nd Ed., American Institute of Physics, New York.
Bodén, A. and Sievänen, U. (2006). Low-pH injection grout for deep repositories. Posiva WR-2005-24, Posiva Oy., Olkiluoto.
Bühler, C., (2005). SELFRAC (SE) Experiment — Long-term dilatometer experiment, Mont Terri Project, Technical Report, TN 2003-17, Mont Terri Rock Laboratory.
BRIGHT User’s Manual (2010). Technical University of Catalonia.
Collin, F., Li, X., Radu, J. P., and Charlier, R. (2002). “Thermo-hydromechanical coupling in clay barriers.” Engineering Geology, Vol. 64, Nos. 2–3, pp. 179–193.
Davies, C. and Bernier, F. (2005). “Impact of the excavation disturbed or damaged zone (EDZ) on the performance of radioactive waste geological repositories.” Proc. of the Eurpean Commission Cluster Conference and Workshop, Luxembourg.
Dixon, D., Chandler, N., Graham, J., and Gray, M. (2002). “Two largescale sealing tests conducted at Atomic Energy of Canada’s underground research laboratory: The buffer-container experiment and the isothermal test.” Can. Geotech. Jnl., Vol. 39, No. 3, pp. 503–518.
European Commission (2004). Geological disposal of radioactive wastes produced by nuclear power: From concept to implementation, European Commission, Belgium.
Falck, W. E. and Nilsson, K. F. (2009). Geological disposal of radioactive waste: Moving towards implementation, JRC Reference Report, JRC European Commission, Washington, D.C.
Fernandez, L., Alonso, M. C., Garcia, J. L., and Hidalgo, A. (2005). “Shotcrete development for low-pH cements.” ESDRED, Proc. of the 2nd Low-pH workshop, Madrid, June 15–16, pp. 161–171.
Gallé, C. (1998). “Migration des gaz et pression de rupture dans une argile compactée destinée á la barriére ouvragée d’un stockage profond.” Bull. Soc. Géol., Vol. 169, No. 5, pp. 675–680.
Gallé, C. (2000). “Gas breakthrough pressure in compacted Fo-Ca clay and interfacial gas overpressure in waste disposal context.” Applied Clay Science, Vol. 17, Nos. 1–2, pp. 85–97.
Gawin, D., Baggio, P., and Schrefler, B. A. (1995). “Coupled heat, water and gas flow in deformable porous media.” Int. J. Numer. Meth. Fluids, Vol. 20, Nos. 8–9, pp. 969–987.
Gens, A. and Alonso, E. E. (1992). “A framework for the behaviour of unsaturated expansive clays.” Can. Geotech. Jnl., Vol. 29, No. 6, pp. 1013–1032.
Gens, A., Sánchez, M., Guimarães, L., Alonso, E., Lloret, A., Olivella, S., Villar, M. V., and Huertas, F. (2009). “A full scale in situ heating test for high level nuclear waste disposal: Observations, analysis and interpretation.” Géotechnique, Vol. 59, No. 4, pp. 377–399.
Graham, J., Halayko, K. G., Hume, H., Kirkham, T., Gray, M., and Oscarson, D. (2002). “A capillarity-advective model for gas breakthrough in clays.” Engineering Geology, Vol. 64, Nos. 2–3, pp. 273–286.
Guimarães, L. Do N., Gens, A., and Olivella, S. (1999). “THM and reactive transport coupling in unsaturated porous media.” Proc. 7th Int. Symp. on Numerical Models in Geomechanics, Graz, pp. 303–308.
Guimarães, L. Do N., Gens, A., and Olivella, S. (2007). “Coupled thermo-hydro-mechanical and chemical analysis of expansive clay subjected to heating and hydration.” Transp. in Porous Media, Vol. 66, No. 3, pp. 341–372.
Guimarães, L., Gens, A., Sánchez, M., and Olivella, S. (2009). “Coupled THMC modelling of unsaturated swelling clays: Constitutive formulation and boundary value problems.” Proc. of 4th Asian Pacific Conference on Unsaturated Soils, Newcastle, Australia, pp. 515–529.
Harrington, J. F. and Horseman, S. T. (2003). Gas migration in KBS-3 buffer bentonite: Sensitivity of test parameters to experimental boundary conditions, SKB TR-03-02, Swedish Nuclear Fuel and Waste Manangement Co., Stockholm.
Heitz, D., Trick, T., and Bühler, C. (2003). SELFRAC (SE) experiment — Long-term plate load experiment, Mont Terri Project, Technical Report, TN 2003-51, Mont Terri Rock Laboratory.
Hoch, A. R., Cliffe, K. A., Swift, B. T., and Rodwell, W. R. (2004). Modelling gas migration in compacted bentonite: GAMBIT club phase 3 final report, POSIVA 2004-02, Posiva Oy., Olkiluoto.
Horseman, S. T. and Harrington, J. F. (1997). Study of gas migration in Mx80 buffer bentonite, BGS International Report WE/97/7, SKB.
Horseman, S. T., Harrington, J. F., and Sellin, P. (1997). “Gas migration in Mx80 buffer bentonite.” Proceedings of the Scientific Basis for Nuclear Waste Management XX, Eds. W.J. Gray and I.R. Triay, Materials Research Society.
Hudson, J. A., Bäckström, A., Rutqvist, J., Jing, L., Backers, T., Chijimatsu, M., Christiansson, R., Feng, X. T., Kobayashi, A., Koyama, T., Lee, H. S., Neretnieks, I., Pan, P. Z., Rinne, M., and Shen, B. T. (2009). “Characterising and modelling the excavation damaged zone in crystalline rock in the context of radioactive waste disposal.” Environmental Geolology, Vol. 57, No. 6, pp. 1275–1297.
Huertas, F., Farina, P., Farias, J., Garcýa-Sineriz, J. L., Villar, M. V., Fernandez, A. M., Martýn, P. L., Elorza, F. J., Gens, A., Sanchez, M., Lloret, A., Samper, J., and Martýnez, M. A. (2006). Full-scale engineered barrier experiment, Updated Final Report, Technical Publication 05-0/2006. Madrid: Enresa.
Hume, H. B. (1999). Gas breakthrough in compacted Avolnea bentonite, MSc Thesis, University of Manitoba, Canada.
IAEA (1993). Report on radioactive waste disposal details, Technical Reports Series No. 349, IAEA, Vienna.
IAEA (1997). Characterization of radioactive waste forms and packages, Technical Reports Series No. 383, IAEA, Vienna.
IAEA (2003a). Scientific and technical basis for the geological disposal of radioactive wastes, Technical Reports Series No. 413, IAEA, Vienna.
IAEA (2003b). Effects of radiation and environmental factors on the durability of materials in spent fuel storage and disposal, IAEATECDOC-1316, IAEA, Vienna.
IAEA (2006). Geological disposal of radioactive waste safety requirements, Safety Standards Series No. WS-R-4, IAEA, Vienna.
IAEA (2010). Nuclear technology review 2010, IAEA, Vienna.
JNC (2000). H12: Project to establish the scientific and technical basis for HLW disposal in Japan-project overview report, JNC TN1410 200-001, Japan Nuclear Cycle Development Institute, Ibaraki.
Kronlöf, A. (2005). Injection grout for deep repositories-low pH cementitious grout for larger fractures: Testing effect of superplasticizer on technical performance, Posiva WR-2005-08, Posiva Oy., Olkiluoto.
Martin, P. L. and Barcala, J. M. (2005). “Large scale buffer material test: Mock-up experiment at CIEMAT.” Engineering Geology, Vol. 81, No. 3, pp. 298–316.
NAGRA (2002). Technical-scientific contributions on the topic of nuclear waste management, NAGRA Bulletin 34, Switzerland.
NAS (1957). The disposal of radioactive waste on land, National Academy of Sciences, NAS Washington, D.C.
National Academies (2006). Geological and geotechnical engineering in the new millennium: Opportunites for research and technological innovation, The National Academies Press, Washington, D.C.
Nuclear Energy Agency (1999). Geological disposal of radioactive waste: Review of developments in the last decade, OECE Nuclear Energy Agency, Paris.
OECD-Nuclear Energy Agency (2003). Engineered barrier systems and the safety of deep geological repositories, Sate-of-the-art Report, OECD-NEA, Paris.
OECD Nuclear Energy Agency (2008). Nuclear energy outlook 2008, NEA, France.
Olivella, S., Carrera, J., Gens, A., and Alonso, E. E. (1994). “Nonisothermal multiphase flow of brine and gas through saline media.” Transport in Porous Media, Vol. 15, pp. 271–293.
Olivella, S., Gens, A., Carrera, J., and Alonso, E. E. (1996). “Numerical formulation for a simulator (CODE-BRIGHT) for the coupled analysis of saline media.” Engineering Computations, Vol. 13, No. 7, pp. 87–112.
Orantie, K. and Kuosa, H. (2007). Durability 2007 injection grout investigation-Background description, Posiva WR-2008-54, Posiva Oy., Olkiluoto.
Pusch, R. and Forsberg, T. (1983). Gas migration through bentonite clay, SKBF/KBS TR-83-71, Swedish Nuclear Fuel and Waste Manangement Co., Stockholm.
Pusch, R., Ranhagen, L., and Nilsson, K. (1985). Gas migration through Mx-80 bentonite, Nagra Technical Report 85-36, Switzerland.
Rutqvist, J., Barr, D., Datta, R., Gens, A., Millard, M., Olivella, S., Tsang, C. F., and Tsang, Y. (2005). “Coupled thermal-hydrologicalmechanical analysis of the Yucca Mountain Drift Scale Test — comparison of field results to predictions of four different models.” Int. J. Rock Mech. & Min. Sci., Vol. 42, No. 5–6, pp. 680–697.
Sánchez, M., Gens, A., Guimarães, L., and Olivella S. (2010). “THM analysis of a large scale heating test incorporating material fabric changes.” Int. Jnl. Numer. Anal. Meth. Geomech, (Accepted).
Sánchez, M., Gens, A., Guimarães, L., and Olivella, S. (2005). “A double structure generalized plasticity model for expansive materials.” Int. Jnl. Numer. Anal. Meth. Geomech, Vol. 29, No. 8, pp. 751–787.
Sánchez, M., Gens, A., Guimarães, L., and Olivella, S. (2008). “Implementation algorithm of a generalized plasticity model for swelling clays.” Computers and Geotechnics, Vol. 35, No. 6, pp. 860–871.
Sievänen, U., Raivio, P., Vuorinen, U., Hansen, J., Norokallio, J., and Syrjänen, P. (2006). Optimization of technical properties of low-pH cementitious injection grout: Laboratory tests and pilot field test 3. Posiva WR-2006-85, Posiva Oy., Olkiluoto.
Svemar, C. and Push, R. (2002). Äspö hard rock laboratory, International Progress Report, IPR-00-30. SKB, Stockholm.
Swedish Nuclear Fuel and Waste Manangement Co.SKB (2004). RD&D-programme 2004, SKB TR-04-21, SKBSwedish Nuclear Fuel and Waste Manangement Co., Stockholm.
Swedish Nuclear Fuel and Waste Manangement Co.SKB (2007). RD&D-programme 2007, SKB TR-07-12, SKBSwedish Nuclear Fuel and Waste Manangement Co., Stockholm.
Tanai, K., Kanno, T., and Gallé, C. (1997). “Experimental study of gas permeabilities and breakthrough pressures in clays.” Proc. of the Scientific Basis of Nuclear Waste Management Conference Number XX, Material Research Society, Boston, USA.
Thomas, H. R. and Cleall, P. J. (1998). “Coupled thermo hydraulic mechanical behaviour of unsaturated soil, including expansive clays.” Workshop on Microstructural Modelling of Natural and Artificially Prepared Clay Soils with Special Emphasis on the Use of Clays for Waste Isolation, (R. Pusch, Ed.), Lund, Sweden, pp. 86–93.
Thomas, H. R. and He, Y. (1995). “An analysis of coupled heat, moisture and air transfer in a deformable unsaturated soil.” Geotechnique, Vol. 45, No. 4, pp. 677–689.
Thomas, H. R., Cleall, P. J., and Hashm, A. A. (2001). “Thermal/Hydraulic/Chemical/Mechanical (THCM) behavior of partly saturated soil.” Computer Methods and Advances in Geomechanics (Desai et al., Eds), A.A. Balkema, Rotterdam, Vol. 1, pp. 756–763.
Torbjörn, H. P., Björn, L., and Carsten, V. (2005). “Selective stabilization of deep core drilled boreholes using low-pH cement.” Proc. 2nd Low-pH Workshop, ESDRED, Madrid, Spain, pp. 122–137.
Tsang, C. F., Bernier, F., and Davies, C. (2005). “Geohydromechanical processes in the excavation damaged zone in crystalline rock, rock salt, and indurated and plastic calys-in the context of radioactive waste disposal.” Int. J. Rock Mech. Min. Sci., Vol. 42, No. 1, pp. 109–125.
Volckaert, G., Dereeper, B., Put, M., Ortiz, L., Gens, A., Vaunat, J., Villar, M. V., Martin, P. L., Imbert, C., Lassabatère, T., Mouche, E., and Cany, F. (2000). A Large-scale in situ demonstration test for repository sealing in an Argillaceous Host Rock, Reseal Phase I Project Report, European Commission, Brussels.
WNA (2009). Radioactive waste management (http://www.worldnuclear.org/info/inf04.html).
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Kim, JS., Kwon, SK., Sanchez, M. et al. Geological storage of high level nuclear waste. KSCE J Civ Eng 15, 721–737 (2011). https://doi.org/10.1007/s12205-011-0012-8
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DOI: https://doi.org/10.1007/s12205-011-0012-8