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Summary ESDRED – An Integrated European Project Focused on Technology Development Wolf K Seidler, Jean-Michel Bosgiraud Andra, France ESDRED (Engineering Studies and Demonstrations of Repository Designs) is an Integrated Project focused on technology development. Over the course of the last 56 months the participants have designed, fabricated, tested and shown a number of static and dynamic demonstrators related to the emplacement of HLLL radioactive waste all of which met or exceeded the design specifications. Other work related to the formulation of low pH cement/concrete/shotcrete mixes and subsequent application/demonstration of these for repository construction and for rock support. Still other work related to the formulation of various material mixes which were then demonstrated as prefabricated or cast in place engineered barriers (or backfill). The results achieved within ESDRED are now on display, or ongoing, at various underground locations including Äspö in Sweden as well as Mont Terri and Grimsel in Switzerland. Andra’s demonstrators have recently been moved to the Saudron Technological Centre near the Bure URL in France while the Ondraf / Euridice work can be seen at the MOL facility in Belgium. DBE TEC’s vertical emplacement demonstrator is set up in the turbine hall of a former thermal power station located near Landesbergen, Germany. All these demonstrators contribute to public confidence building, regarding the societal issues related to underground disposal of radioactive waste. 1. Introduction The Integrated Project known as ESDRED has been a joint research and development effort by major national radioactive waste management agencies (or subsidiaries of those agencies) and by research organisations. ESDRED was co-ordinated by the French National Radioactive Waste Management Agency (Andra). The original five year budget of <strong>EU</strong>RO 18.4 million, of which 7.3 million was provided by the European Commission (EC), was overspent because several of the participants elected to do either more work or more elaborate work than originally envisaged. The 13 participants (Contractors) in this project, from 9 European countries, are: Radioactive Waste Management Agencies: Technological R&D Organisations: ANDRA, France AITEMIN, Spain ENRESA, Spain CSIC, Spain NAGRA, Switzerland DBE TECHNOLOGY, Germany NDA (Originally NIREX), United Kingdom ESV <strong>EU</strong>RIDICE EIG, Belgium ONDRAF/NIRAS, Belgium GRS, Germany POSIVA, Finland NRG, the Netherlands SKB, Sweden 229
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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
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
Page 214 and 215: in the underground laboratory in Gr
Page 216 and 217: under isothermal conditions. If the
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Page 220 and 221: Zones around such openings which ex
Page 222 and 223: layout of cells developed by ENPC w
Page 224 and 225: ) a) e) d) f) d) e) f) c) Figure 3.
Page 226 and 227: EDZ removal by additional excavatio
Page 228 and 229: [7] Wenk H.-R., Voltolini, M., Mazu
Page 230 and 231: that provided by various national s
Page 232 and 233: system robustness, rather than as s
Page 234 and 235: Regarding diffusion studies perform
Page 236 and 237: 7. EDZ characterization and evoluti
Page 238 and 239: [4] Alonso, J. et al. 2004: Bentoni
Page 240 and 241: There has been a significant change
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Page 246 and 247: 2. Methodology ESDRED has been focu
Page 248 and 249: Figure 3: Reduced scale mock-up aft
Page 250 and 251: Figure 8: Demonstration of emplacem
Page 252 and 253: The various reports produced by the
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Page 256 and 257: 2. Methodology In general, the work
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Page 260 and 261: Figure 3.2.1 Schematic representati
Page 262 and 263: which was relatively homogeneous in
Page 264 and 265: Figure 3.3.1 Emplacement of SF-Cani
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Page 268 and 269: the outlet with some pressure and f
Page 270 and 271: A experiment, using cross-hole seis
Page 272 and 273: This seal will be implemented as ri
Page 274 and 275: [6] Miehe, R., Kröhn, P., Moog, H.
Page 276 and 277: dence. For waste canister transport
Page 278 and 279: The main waste canister characteris
Page 280 and 281: placement borehole. The BSK 3 canis
Page 282 and 283: Figure 6: Sketch of the Pushing Rob
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Page 286 and 287: 1.1 Water Cushion Application SKB (
Page 288 and 289: In the case of SKB and Posiva, the
Page 290 and 291: Deposition machine tests with load
Page 292 and 293: 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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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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