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5. Conclusions The HLW arising from advanced fuel cycles generates less heat than the spent fuel arising from the reference once-through fuel cycle. This would allow the dimensions of the geological repository to be reduced. The total doses due to geological disposal of spent fuel, HLW and ILW are dominated by contributions from mobile fission and activation products (actinides being immobile due to very high sorption and solubility limitation). As a consequence the transmutation of actinides in fast reactors or ADS would have little impact on the resulting doses in the case of the considered reference scenario. On the other hand, the removal or capture of 129 I upon reprocessing could have a much stronger impact on the maximum dose. Considerable amounts of mobile activation products, such as 14 C, are calculated to be generated in advanced fuel cycles and, consequently, to give a significant contribution to the total dose; this observation confirms the importance of developing low activation fuel matrices and construction materials for future nuclear reactors. The radiotoxicity in the HLW from advanced fuel cycles, after a few centuries cooling time, is drastically reduced by the transmutation of the actinides. Although this would lead to a considerable reduction of the potential hazard in the case of inadvertent human intrusion, the use of this variant scenario as a decision making tool for long-term radioactive waste management is highly debatable. 6. Acknowledgements This project has been co-funded by the European Commission and performed as part of the 6 th Euratom Framework Programme for nuclear research and training activities (2002-2006) under contract FI6W-CT-2004-002408. References [1] V. Bhatnagar, S. Casalta and M. Hugon (2005) Partitioning and Transmutation Research in the Euratom 5 th and 6 th Framework Programmes. Proc. 8 th Information Exchange Meeting on P&T, Las Vegas, 9-11 November 2004. Nuclear Energy Agency, Paris. [2] V. Bhatnagar and G. Van Goethem (2007) Overview of the EU Activities on Partitioning and Transmutation Research in the Euratom 6 th and 7 th Framework Programmes. Proc. 9 th Information Exchange Meeting on P&T, Nîmes, 25-29 September 2006. Nuclear Energy Agency, Paris. [3] Actinide and Fission Product Partitioning and Transmutation; Status and Assessment Report (1999) Nuclear Energy Agency, Paris. [4] Accelerator-driven Systems (ADS) and Fast Reactors (FR) in Advanced Nuclear Fuel Cycles: A Comparative Study (2002) Nuclear Energy Agency, Paris. [5] Impact of Advanced Nuclear Fuel Cycle Options on Waste Management Policies (2006) Nuclear Energy Agency, Paris. [6] Accelerator Driven Systems: Energy Generation and Transmutation of Nuclear Waste: Status Report (1998) International Atomic Energy Agency, Vienna, Report TECDOC 985. [7] Implications of Partitioning and Transmutation in Radioactive Waste Management (2004) International Atomic Energy Agency, Vienna, Technical Reports Series No. 435. [8] A Technical Roadmap for Generation IV Nuclear Energy Systems (2003) US Department of Energy, Nuclear Energy Research Advisory Committee, Washington, Report GIF-002-00. 150
[9] W. von Lenza, R. Nabbi and M. Rossbach (Eds.) (2008) Red-Impact: Impact of Partitioning, Transmutation and Waste Reduction Technologies on the Final Nuclear Waste Disposal. FZ Jülich, Report Vol. 15. [10] E. González (2008) Impact of partitioning and transmutation on nuclear waste management and the associated geological repositories. Proc. Euradwaste '08 Conference (in preparation). [11] SAFIR 2: Safety Assessment and Feasibility Interim Report (2001) ONDRAF/NIRAS, Brussels, Belgium, Report NIROND 2001-06 E. [12] M.Kelly and C.P. Jackson (2007) User Guide for SHIM Version 5.0. Serco Assurance Report to UK Nirex, Report SA/ENV-0557. [13] Radiation Protection Recommendations as Applied to the Disposal of Long-lived Solid Radioactive Waste (2000) ICRP Publication 81, Annals of the ICRP, 28, 4. 151
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Interested in European research? Re
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LEGAL NOTICE Neither the European C
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TABLE OF CONTENTS FOREWORD iii CONF
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“Impact of advanced fuel cycle sc
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“Sensitivity analysis techniques
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Topic: Support actions SAPIERR-II -
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CONFERENCE SUMMARIES
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supported. The Commission believes
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Ms Monika Hammarström of SKB in Sw
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Dr Bruno of Amphos 21 urged the swi
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measurements of actinides to determ
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Dr Peter Blümling of Nagra in Swit
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Future directions There seemed to b
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1. Introduction Keynote Address Pet
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tive waste management, a considerab
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the decision making process. The se
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All initiatives leading to encourag
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tegrating them as part of advanced
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General introduction and objectives
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Radioactive waste management: Where
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The intense development in nuclear
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Figure 3: Schematic diagram of the
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contributed to enhance knowledge ab
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the first time in French history, a
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PANEL DISCUSSION Summary of the Pan
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With the support of IAEA preliminar
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Assessment of Financial Provisions
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collected in the cost of the nuclea
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erated by Fortum) and one PWR unit
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pected. As to tunnel backfilling, t
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ferent, the technological solutions
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Discussion: As a response to a ques
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Cooperation in the development of g
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During the 1980’s it was realized
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government on the operating license
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tions. EDRAM is another example of
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Discussion: The chairman opened the
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Communicating the safety of radioac
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Communicating the Safety of Radioac
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Geological repositories … Differe
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Geological long-term stability (pla
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Times & doses in perspective (examp
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Trust is generated (by the regulato
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4. The regulators could play a very
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Europe's nuclear industries, theref
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filled - one key example being coll
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Table 2. FP6 Integrated Projects an
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EUROTRANS focuses on the transmutat
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Page 122 and 123: significantly reduce the quantities
Page 124 and 125: Pyrochemical processes rely on refi
Page 126 and 127: Figure 3: Schematic layout of an el
Page 128 and 129: Considering pyrochemistry technolog
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Page 132 and 133: Table 1: Fuels irradiated in the SU
Page 134 and 135: lead cooling (see Fig. 5). Alternat
Page 136 and 137: Figure 6: Principle design characte
Page 138 and 139: Table 6: FUTURIX FTA fuels Fuel nam
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Page 142 and 143: After a review of the present statu
Page 144 and 145: suranium elements, “repository av
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Page 148 and 149: high level waste at the considered
Page 150 and 151: Pu or M.A. by the time it is needed
Page 152 and 153: of U and Pu only. P&T could complem
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Page 156 and 157: Phase-Out TRU Transmutation Scenari
Page 158 and 159: 10 nuclear nations (Argentina, Braz
Page 160 and 161: elease, strong radiation, pressure
Page 162 and 163: A1 3.79E+08 270 7.12E-07 A2 3.51E+0
Page 164 and 165: nuclear fission in the reactors. Th
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Page 170 and 171: tinides (MA) are destined for geolo
Page 172 and 173: [3] Enrique González: Head of Nucl
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Page 178 and 179: erage level of funding of research
Page 180 and 181: Prior to NF-PRO, the question wheth
Page 182 and 183: nant exchangeable cation. This chan
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Page 186 and 187: access shafts, providing higher per
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Page 190 and 191: in the European coordinated action
Page 192 and 193: proved, with amongst others the det
Page 194 and 195: 4. Discussion Tests with dissolved
Page 196 and 197: though with a slow rate. The data i
Page 198 and 199: surface. The coupling between water
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Page 202 and 203: tion of the column [2]. Moreover, t
Page 204 and 205: case, the iron diffusion front in t
Page 206 and 207: 5.1 Sorption As an example of the t
Page 208 and 209: corrosion; up-scaling of clay alter
Page 210 and 211: Bentonite barriers are very importa
Page 212 and 213: To determine the impact of temperat
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under isothermal conditions. If the
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202
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Zones around such openings which ex
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layout of cells developed by ENPC w
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) a) e) d) f) d) e) f) c) Figure 3.
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EDZ removal by additional excavatio
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[7] Wenk H.-R., Voltolini, M., Mazu
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that provided by various national s
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system robustness, rather than as s
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Regarding diffusion studies perform
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7. EDZ characterization and evoluti
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[4] Alonso, J. et al. 2004: Bentoni
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There has been a significant change
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226
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228
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2. Methodology ESDRED has been focu
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Figure 3: Reduced scale mock-up aft
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Figure 8: Demonstration of emplacem
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The various reports produced by the
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238
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2. Methodology In general, the work
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limitations of the selected press.
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Figure 3.2.1 Schematic representati
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which was relatively homogeneous in
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Figure 3.3.1 Emplacement of SF-Cani
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1.650 1.600 1.550 1.500 1.450 1.400
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the outlet with some pressure and f
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A experiment, using cross-hole seis
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This seal will be implemented as ri
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[6] Miehe, R., Kröhn, P., Moog, H.
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dence. For waste canister transport
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The main waste canister characteris
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placement borehole. The BSK 3 canis
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Figure 6: Sketch of the Pushing Rob
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268
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1.1 Water Cushion Application SKB (
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In the case of SKB and Posiva, the
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Deposition machine tests with load
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Figure 10: Details of electrical pu
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the very heavy weight (43 ton) of t
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is no experience in either the work
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the case of the long plug elaborate
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values measured in the percolated w
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plug the concrete was mixed manuall
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2.3 Testing of low-pH shotcrete for
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290
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energy is produced by fission of ur
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3.2. Integration 3.2.1. Pool Facili
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3.4. Education and Training Apart f
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298
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Fig. 1.1: EU Member States involved
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Fig. 1.3: Stakeholders and interest
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- Present state of scientific level
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6. Training courses Key events of t
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308
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materials, the essential aspects of
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2.1 Geological formation scale (10
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porosity outside the clay interlaye
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eduction in De with increasing prop
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well-defined profile, with the high
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Th(IV) sorption on montmorillonite
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RN migration experiments and model
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tion/organization and its Cu(II) re
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326
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ganic/organic colloids”; WP 4.5
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Figure 1: Schematic of the FEBEX dr
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within feldspars in the three grani
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Colloid Concentration (ppm) 160 140
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form. Clay colloids were detected i
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References [1] Retrock (2005). Trea
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vance on radionuclide migration. Ma
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342
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The Ruprechtov site, located in the
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Colloid Concentration / μg/l 10000
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exists as a stable mineral phase in
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pared to other sites with SOC-beari
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[3] Hauser, W. Geckeis, H., Götz,
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The science and technology group, r
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FEPCAT RTDC 1 RTDC 2 RTDC 3 Clay-ri
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A1: Transport mechanisms Diffusivit
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360
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maintaining and develop competence
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A project would be justified to det
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366
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368
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The main goal of RTDC-1 is to provi
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3. RTDC3 In RTD component 3 methodo
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lower depths are less saline. For t
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[3] Marivoet, J., Beuth, T., Alonso
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certainty, conducted in RTDC-1 as W
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A simplistic summary might place PA
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There are at least three non-numeri
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10-11 June 2008. The workshop was a
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Close dialogue between a regulator
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ony, interactions, etc., and to che
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specific sampling strategy, with th
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2.2.3 Graphical methods Let us call
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3. The sensitivity analysis benchma
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4. Discussion and conclusions Three
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398
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2. Methodology The project particip
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Closely related to this proposal on
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4.3 Structure The TP structure must
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4.5 Implementation It is proposed t
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5.1 The CARD Project has shown that
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� What steps should be taken to m
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412
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414
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materials. For attaining the stated
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the bottom of the heated press-mold
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420
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422
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focuses on the study of the combine
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emitting radioactive waste to study
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428
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2.1 Laboratory experiment The dispo
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3. Results 3.1 Laboratory experimen
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Barrier. Clays in Natural & Enginee
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2. Experimental data 2.1 Laboratory
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sented in the accompanying poster,
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440
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situ stress to model the gallery ex
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tive crack network, oriented along
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446
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ous reasons, SCK•CEN chose to foc
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lery, are already monitoring temper
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[1] Bernier F., Li X.L., Weetjens E
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Concrete The cement used is an Ordi
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Brucite Ettringite 10 �m 8 �m F
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458
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2. Methodology In the case of cylin
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cell dismantled after 6 months, roo
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[3] G.E. Gdowski, Humid Air Corrosi
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crucial to predict the hydration ra
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load is higher, since the load appl
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[4] Gens, A. & Alonso, E. 1992. A f
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2. Experimental Methodology A salt
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proof of healing in salt rocks. It
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476
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obtained experimental results [1].
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dependent shear strength softening
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482
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elease falls typically between 1 an
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Figure 3: Left: Spent fuel surface
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488
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1. Data compilation and evaluation
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Volumetric deformation [%] 20 18 16
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An overview of the test procedure w
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496
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The works performed within RTDC-1 p
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Integrated Project “Fundamental P
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502
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The Ruprechtov natural analogue sit
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esults and integrated to develop a
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508
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510
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from 12.5 to 13.5, have high ionic
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elative intensity (cps) 8000 6000 4
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516
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518
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2. SAPIERR I and II In Europe, the
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after extensive interactions have t
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eing partners if an ERDO is formall
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526
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2. Methodology Based on existing da
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external funds ensuring the indepen
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532
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534
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Mr Jozef BALAZ JAVYS, a.s. - Nuclea
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Prof. Gunnar Johan BUCKAU Forschung
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Dr Mario DIONISI APAT - Dipartiment
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Dr Paloma GÓMEZ GONZÁLEZ CIEMAT -
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Ms Aurélie JESTIN SOGEDEC Z.I. Dig
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Dr Patrick MAJERUS Ministry of Heal
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Mr Zoltán NAGY PURAM - Department
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Ms Katerina PTACKOVA European Commi
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Prof. Christian SCHRÖDER Universit
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Dr Ján TIMUL'ÁK DECOM Slovakia, s
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Dr. Eng. Shuichi YAMAMOTO Obayashi
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