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� What steps should be taken to maximise the associated benefits from coordinated RD&D such as training or information exchange? The view was expressed that the experience gained from recent EC Framework Programmes in the field of radioactive waste management science and technology has been very beneficial to training and information exchange in European programmes. Therefore there is a successful model already in existence that should be built upon. The main development that was urged was the integration of engineering into the strategic research agenda of a future technology platform. This resonated with the discussion in response to the first question. � How can the benefits of coordinated RD&D be maximised for national programmes with relatively small scientific and technical resources? There was a clear statement on behalf of such national programmes that coordinated RD&D, such as would be conducted in the framework of a technology platform, is vital to their success. Effective communication of the motivation of the RD&D programme and of its outputs, to make this information accessible to a wide range of stakeholders, will help to maximise the benefits. � Are there reservations or constraints to bear in mind when considering coordination of strategic RD&D? The main issue identified was the importance of an RD&D activity to a key decision point in a national programme. Whereas an activity might be highly suitable for inclusion in a coordinated programme in a technical sense, the implementing organisation might legitimately require managing the risk to the national programme by retaining total control over the activity to ensure delivery of the required information on the required timescale. However, successful operation of a technology platform in its early years might well give confidence that such programme risks could be managed equally effectively in the resulting coordinated international programme and that the foreseen benefits of involvement in the coordinated programme would outweigh the negligible risk from relinquishing individual control. 410
Posters based on projects performed as part of Euratom FP6, ISTC and supported by the EC-DG Energy and Transport (TREN) 411
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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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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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Page 386 and 387: The main goal of RTDC-1 is to provi
Page 388 and 389: 3. RTDC3 In RTD component 3 methodo
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Page 408 and 409: 2.2.3 Graphical methods Let us call
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Page 416 and 417: 2. Methodology The project particip
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Page 420 and 421: 4.3 Structure The TP structure must
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Page 432 and 433: materials. For attaining the stated
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Page 440 and 441: focuses on the study of the combine
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Page 446 and 447: 2.1 Laboratory experiment The dispo
Page 448 and 449: 3. Results 3.1 Laboratory experimen
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Page 452 and 453: 2. Experimental data 2.1 Laboratory
Page 454 and 455: sented in the accompanying poster,
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Page 458 and 459: situ stress to model the gallery ex
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Page 464 and 465: ous reasons, SCK•CEN chose to foc
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Page 468 and 469: [1] Bernier F., Li X.L., Weetjens E
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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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