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Another important development is that the European Council endorsed in March 2007 a Commission proposal to set up an EU High Level Group on Nuclear Safety and Waste Management. The mandate of the group is to progressively develop a common understanding in these fields and, eventually, to suggest additional European rules. This work has to take into account a set of actions formulated in Council Conclusions in May 2007. Triggering progress in Radioactive Waste Management is forming an important objective and again, a dedicated Subgroup has been created to cover a number of issues, including obstacles and drivers, the better use of the Joint Convention process, guidelines for national programmes as well as the use of best practices and peer reviews. Finally let's talk about Research and a very recent initiative to create a Technological Platform on the IMPLEMENTATION of Geological Disposal of Radioactive Waste. Following a feasibility study, an interim Executive Group under Swedish leadership is right now developing a Vision Document describing the possible scope and objectives of this Platform. The group arrived at the view that after decades of extensive research, development and technical demonstration the time is ripe now to focus on the implementation of geological disposal without further delay. It is no surprise that the draft vision suggests to cover three key topics: confidence building, establishment of national waste management plans as well as facilitating and maintaining access to existing competence and technology. The Technological Platform is scheduled to be launched during 2009. We very much hope and expect that these three initiatives will lead to significant progress in Radioactive Waste Management. 5. Conclusions In summary, I would like to offer the following conclusions for your consideration. Following 30 years of research, geological disposal now represents a passively safe and sustainable option for the long-term management of high-level waste, also proven by natural analogues. European citizens attach to this issue a high importance. There are solutions as regards all technical, financial and societal aspects. – It is therefore time to implement this solution, independent from medium- to longterm national energy policies. Wait-and-see approaches putting burdens on future generations and certainly waste export to countries outside the EU should not be supported. – The Commission believes that the eventual implementation of deep geological disposal is an essential condition for the continued use and possible expansion of nuclear power. 20
All initiatives leading to encouraging and facilitating progress towards identification and operation of waste repositories are therefore highly welcome. The Commission also expects that the High Level Group will address without delay the action imposed on them by the Council Conclusions of 8 May 2007: – to clearly identify the need for "developing strategies for the safe management of all types of spent fuel and radioactive waste" and – to "urge EU Member State to establish and keep updated a national programme for the safe management of radioactive waste and spent fuel that includes all radioactive waste under its jurisdiction and covers all stages of management." The Commission also has high expectations in the driving forces of ENEF and the guidance it will provide. The same applies to the planned new Technological Platform on the Implementation of Geological Disposal of Radioactive Waste. This first day of the Euradwaste conference will address many of issues I mentioned before, the situation, the obstacles and drivers, the question of economics, and finally the important issue of public trust. We trust that this day will form a further important piece in the puzzle towards final solutions. In any case I hope that you will experience today interesting and fruitful debates. I am sure, this will not be the last time we discuss these issues. But I have a dream: at the Euradwaste 2012 the Commission comes up with a Keynote Speech, which has got nothing but good messages. Geological processes last long, but even they lead to changes from time to time… I thank you for your attention. 21
Page 2 and 3: Interested in European research? Re
Page 4 and 5: LEGAL NOTICE Neither the European C
Page 7 and 8: TABLE OF CONTENTS FOREWORD iii CONF
Page 9 and 10: “Impact of advanced fuel cycle sc
Page 11 and 12: “Sensitivity analysis techniques
Page 13 and 14: Topic: Support actions SAPIERR-II -
Page 15: CONFERENCE SUMMARIES
Page 18 and 19: supported. The Commission believes
Page 20 and 21: Ms Monika Hammarström of SKB in Sw
Page 22 and 23: Dr Bruno of Amphos 21 urged the swi
Page 24 and 25: measurements of actinides to determ
Page 26 and 27: Dr Peter Blümling of Nagra in Swit
Page 28 and 29: Future directions There seemed to b
Page 31 and 32: 1. Introduction Keynote Address Pet
Page 33 and 34: tive waste management, a considerab
Page 35: the decision making process. The se
Page 40 and 41: tegrating them as part of advanced
Page 43: General introduction and objectives
Page 47 and 48: Radioactive waste management: Where
Page 49 and 50: The intense development in nuclear
Page 51 and 52: Figure 3: Schematic diagram of the
Page 53 and 54: contributed to enhance knowledge ab
Page 55 and 56: the first time in French history, a
Page 57 and 58: PANEL DISCUSSION Summary of the Pan
Page 59: With the support of IAEA preliminar
Page 63 and 64: Assessment of Financial Provisions
Page 65 and 66: collected in the cost of the nuclea
Page 67 and 68: erated by Fortum) and one PWR unit
Page 69 and 70: pected. As to tunnel backfilling, t
Page 71 and 72: ferent, the technological solutions
Page 73 and 74: PANEL DISCUSSION Summary of the Pan
Page 75: Discussion: As a response to a ques
Page 79 and 80: Cooperation in the development of g
Page 81 and 82: During the 1980’s it was realized
Page 83: 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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PANEL DISCUSSION Summary of the Pan
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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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consensus that geological disposal
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102
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104
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significantly reduce the quantities
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Pyrochemical processes rely on refi
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Figure 3: Schematic layout of an el
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Considering pyrochemistry technolog
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agreed for support through an integ
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Table 1: Fuels irradiated in the SU
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lead cooling (see Fig. 5). Alternat
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Figure 6: Principle design characte
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Table 6: FUTURIX FTA fuels Fuel nam
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124
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After a review of the present statu
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suranium elements, “repository av
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nificant fraction of fast reactors.
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high level waste at the considered
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Pu or M.A. by the time it is needed
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of U and Pu only. P&T could complem
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suranium elements, the thermal load
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Phase-Out TRU Transmutation Scenari
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10 nuclear nations (Argentina, Braz
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elease, strong radiation, pressure
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A1 3.79E+08 270 7.12E-07 A2 3.51E+0
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nuclear fission in the reactors. Th
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5. Conclusions The HLW arising from
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152
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tinides (MA) are destined for geolo
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[3] Enrique González: Head of Nucl
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158
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160
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erage level of funding of research
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Prior to NF-PRO, the question wheth
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nant exchangeable cation. This chan
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eal concentration gradient in sampl
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access shafts, providing higher per
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172
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in the European coordinated action
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proved, with amongst others the det
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4. Discussion Tests with dissolved
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though with a slow rate. The data i
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surface. The coupling between water
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nuclear waste within the near-field
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tion of the column [2]. Moreover, t
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case, the iron diffusion front in t
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5.1 Sorption As an example of the t
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corrosion; up-scaling of clay alter
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Bentonite barriers are very importa
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To determine the impact of temperat
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in the underground laboratory in Gr
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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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