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Repository design

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Prefabricated EBS module development was driven, in many cases, by the desire to improve the practicality of remote emplacement of engineered barriers in a safer and quality-assured manner. This is particularly critical in wetter host rocks, where handling of compacted bentonite becomes problematic. Such modules have also been designed for much larger spent fuel overpacks. A clear variant would thus be modules containing several HLW packages in a single overpack – which could lead to significant savings of cost and handling time.

The lack of precedent for HLW disposal has, however, led to a call for slow, staged implementation which is monitored and easily reversible for a long institutional control period. To provide a disposal system which meets this requirement needs alternative repository design options, which could have additional attractions from the viewpoint of long-term safety. This long-term institutional control certainly raises issues associated with operational safety during this period (especially considering perturbations such as earthquakes, civil disturbances, etc.), but also has significant advantages due to its small footprint and, possibly, the long-term performance of the sealed system (Masuda et al., 2004).

Taking the catalogue of the design options, NUMO, e.g., have formulated a logical system for guiding the concept development process (Figure 5.10). As indicated, there are pre-defined exclusion criteria which would result in locations which are unsuitable in terms of geological stability being excluded from further consideration. Sites which are sufficiently stable may, nevertheless, have clearly better or poorer geological/hydrogeological conditions. Sites which are less favourable may be placed in a reserve class. Conceptual studies have indicated that various options exist to compensate for poorer site characteristics by enhancing engineered barriers (e.g., hydraulic cage or barrier concepts). Extensive R&D would be required to fully assess the feasibility of such designs.

In response to the challenge to derive safe and acceptable repository concepts for any potentially suitable location, advantage can be taken of international knowledge databases to develop alternative repository design options. Preliminary work has confirmed that many options are available to tailor designs to both the geological environment available and the particular socio-political constraints set, e.g., by the host community. The extra workload on the scientists and technologies involved is significant but will be completely justified if the resulting repository project can be implemented with the full support of the local community.

5.7. References

Adler, M., Ma¨der, U., Waber, N. (1999). High-pH alteration of argillaceous rocks: an experimental study.

Schweiz. Mineral. Petrogr. Mitt. 79, 445–454.

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Aikas, T. (2003). Managing Design Requirements in Crystalline Rock. In Proc. of Workshop on Engineered Barrier Systems (EBS) in the Context of the Entire Safety Case. OECD/NEA, Paris, France, pp. 41–42.

ANDRA (2001). DOSSIER 2001 ARGILE, Progress Report on Feasibility Studies & Research into Deep Geological Disposal of High-Level, Long-Lived Waste, Synthesis Report, December 2001, Andra, Paris, France.

Bel, J., De Bock, C. Boyazis, J-P. (2004). Comparing Technical Concepts for Disposal of Belgian Vitrified HLW, Proc. of Workshop on Engineered Barrier Systems (EBS): Design Requirements and Constraints, OECD/NEA Report No. 4548, OECD/NEA, Paris, France, pp 87–99.

Biggin, C., Alexander, W.R., Kickmaier, W., McKinley, I.G. (2003). Integrated programme of research into the behaviour of the clay engineered barrier: an example from Nagra’s Grimsel Test Site. In: Clays and natural

142

H. Umeki

and engineered barriers for radioactive waste confinement: experiments in underground laboratories. Reims, 9–12 December, 2002. Andra Science and Technology Report Series, Andra, Paris, France, pp 18–27.

EC-NEA (2003). Engineered Barrier Systems and the Safety of Deep Geological Repositories, State-of-the-art Report, EU report EUR 19964 EN, EC, Brussels, Belgium.

ENRESA (2000). Full-scale engineered barriers experiment for a deep geological repository for high level radioactive waste in crystalline host rock, final report. Enresa technical publication 1/2000, Enresa, Madrid, Spain.

FEPC & JAEA (in preparation). The Second Progress Report (TRU-2) on the R&D for TRU (ILW) waste disposal in Japan. JAEA Report (in press). JAEA, Tokai, Japan.

Gierszewski, P.J., Russell, S.B., Garisto, F., Jenson, M.R., Kempe, T.F., Maak, P., Simmons, G.R. (2001). Deep Geologic Repository Technology Program – Annual Report 2000, Report No: 06819 - REP - 01200 - 10055 - R00, OPG, Toronto, Canada.

IAEA (1995). The Principles of Radioactive Waste Management, Safety Series No. 111-F, IAEA, Vienna, Austria.

IAEA (1997). Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, INFCIRC/546, IAEA, Vienna, Austria.

IAEA (1999). Review of the factors affecting the selection and implementation of waste management technologies, TECDOC-1096, IAEA, Vienna, Austria.

IAEA (2001). Monitoring of geological repositories for high level radioactive waste, TECDOC-1208, IAEA, Vienna, Austria.

ICRP (2000). Radiation Protection Recommendations as Applied to the Disposal of Long lived Solid Radioactive Waste, International Commission on Radiological Protection, ICRP Publication no. 81, Pergamon Press, Oxford and New York.

JNC (2000). H12: Project to establish the scientific and technical basis for HLW disposal in Japan, Project Overview Report, 2nd progress report on research and development for the geological disposal of HLW in Japan, JNC TN1410 2000-001, JNC, Tokai, Japan.

Jing, L., Stephansson, O., Tsang, C-F., Kautsky, F. (1996). DECOVALEX – Mathematical Models of Coupled T-H-M Processes for Nuclear Waste Repositories, Executive Summary for Phases I, II and III. www.decovalex.com.

Lindgren, E., Pettersson, S., Salo, J.-P. (2003). R&D program for Horizontal Emplacement KBS-3H, Proc. of 10th International High-Level Radioactive Waste Management Conference (IHLRWM 2003), 30 March– 2 April 2003, Las Vegas, American Nuclear Society, Washington DC, USA, pp 571–577.

Ma¨der, U., Frieg, B., Puigdomenech, I., Decombarieu, M., Yui, M. (2004). Hyperalkaline cement leachate-rock interaction and radionuclide transport in a fractured host rock (HPF Project). Sci Basis Nucl Waste Manag XXVII, 861–866.

Masuda, S., Umeki, H., McKinley, I.G., Kawamura, H. (2004). Management with CARE, Nuclear Engineering International 49, No. 604, November, 2004.

McKinley, I.G. (1985). The geochemistry of the near-field. Nagra Technical Report Series NTB 84-48, Nagra, Wettingen, Switzerland.

Miller, W., Alexander, W.R., Chapman, N., McKinley, I.G., Smellie, J. (2000). Geological Disposal of Radioactive Wastes and Natural Analogues, Elsevier, Amsterdam, The Netherlands.

Nagra 1985. Projekt Gewa¨hr 1985. vol. 9 (English summary). Nagra Gewa¨hr Report Series NGB 85-09. Nagra, Wettingen, Switzerland.

Nagra 1994. Kristallin-1. Safety assessment report. Nagra Technical Report NTB 93-22, Nagra, Wettingen, Switzerland.

Nagra (1999). Synthesis of the Geological Investigations at Wellenberg, Nagra Bulletin No. 32, Nagra, Wettingen, Switzerland.

Nagra (2002). Project Opalinus Clay, Safety Report, Demonstration of Disposal Feasibility for Spent Fuel, Vitrified High-level Waste and Long-lived Intermediate-level Waste (Entsorgungsnachweis), Nagra Technical Report NTB 02-05, Nagra, Wettingen Switzerland.

NEA (1999). Confidence in the Long-term Safety of Deep Geological Repositories, Its Development and Communication, OECD/NEA, Paris, France.

NEA (2001). Reversibility and Retrievability in Geologic Disposal of Radioactive Waste, Reflections at the International Level, OECD/NEA, Paris, France.

NEA (2002). Establishing and Communicating Confidence in the Safety of Deep Geologic Disposal, OECD/ NEA, Paris, France.

Repository design

143

NEA (2003). Engineered Barrier Systems (EBS) in the Context of the Entire Safety Case, Workshop Proc., OECD/NEA, Paris, France.

NUMO (2004). Development of Repository Concepts for Volunteer Siting Environments, NUMO Technical Report TR-04-03, NUMO, Tokyo, Japan.

ONDRAF (2001a). Technical overview of SAFIR 2: SA and feasibility interim report 2, ONDRAF/NIRAS Technical Report NIROND 2001-05 E, ONDRAF/NIRAS, Brussels, Belgium.

ONDRAF (2001b). SAFIR 2: SA and Feasibility Interim Report 1, ONDRAF/NIRAS Technical Report NIROND 2001-06 E, ONDRAF/NIRAS, Brussels, Belgium.

Posiva (1999). The Final Disposal Facility for Spent Nuclear Fuel – Environmental Impact Assessment Report, Posiva Oy, Rauma, Finland.

Posiva (2000). Disposal of Spent Fuel in Olkiluoto Bedrock, Programme for Research Development and Technical Design for the Pre-Construction Phase, Posiva Oy Report No. 2000-14, Rauma, Finland.

SKB (1992). Project on alternative system study (PASS), Final report, SKB Technical Report TR 99-08, SKB, Stockholm, Sweden.

SKB (1998). RD&D-Programme 98, Treatment and final disposal of nuclear waste, Programme for research, development and demonstration of encapsulation and geological disposal, SKB, Stockholm, Sweden.

SKB (2001). RD&D-Programme 2001, Programme for Research, Development and Demonstration of Methods for the Management and Disposal of Nuclear Waste, SKB Technical Report TR 01-30, SKB, Stockholm, Sweden.

Smellie, J.A.T., Alexander, W.R., Degnan, P., Griffault, L.Y., Ma¨der, U.K., Trotignon, L. (2001). The role of the Jordan natural analogue studies in the performance assessment of cementitious repositories for radioactive wastes. In: 10th Int. Water Rock Interaction Symposium, Villasimius, Italy. (June 10–15, 2001), Balkema, Amsterdam, The Netherlands, pp 1391–1393.

Soler, J.M., Ma¨der, U.K. (2002a). The GTS-HPF experiment: Reaction-induced permeability changes.

Geochim Cosmochim Acta 66, (Supplement 1), A726.

Soler, J.M., Ma¨der, U.K. (2002b). High-pH plume. Reactive transport simulations. In: Metz, V., Pfingsten, W., Lu¨tzenkirchen, J., Schu¨ssler, W. (Eds.), TRePro 2002. Modelling of Coupled Transport Reaction Processes. Forschungszentrum Karlsruhe, Technik und Umwelt, Wissenschaftliche Berichte FZK 6721, pp 97–100.

Thompson, P., Baumgartner, P., Ales, Y., et al. (2003). An approach to long-term monitoring for a nuclear fuel waste repository, OPG -06819-REP-01200-10105R00, OPG, Toronto, Canada.

U.S. DOE (2002). Yucca Mountain Science and Engineering Report Rev.1, Technical Information Supporting Site Recommendation Consideration, DOE/RW-0539-1, U.S. Department of Energy, Office of Civilian Radioactive Waste Management, Washington DC, USA.

Walker, C., Metcalfe, R. (Eds.) (2004). Proceedings of the International Workshop on Bentonite-Cement Interaction in Repository Environments, 14–16 April 2004, Tokyo, Japan, NUMO, TR-04–05 (also published as Posiva Working Report 2004–05), NUMO, Tokyo, Japan.