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[4] Alonso, J. et al. 2004: Bentonite barriers in Integrated Performance Asseessment (BENIPA), FIKW-CT-2000-00015, EUR 21023. [5] Huertas, F. et al. 2005: Final Report, FEBEX-II, Full-Scale Engineered Barriers Experiment for a Deep Geological Repository for High-Level Waste in Crystalline Host Rock – Phase II, EUR 21922. [6] Rodwell, W. et al. 2003: A Thematic Network on Gas Issues of Deep Repositories for Radioactive Waste (GASNET), FIKW-CT-2001-20165, EUR 20620. [7] Becker, D. et al.2002: Testing of Safety and Performance Indicators (SPIN), FIKW- CT2000-00081, EUR 19965. [8] Grambow et al. 2008: RTDC-1 Final Synthesis Report, Dissolution and release from the waste matrix. EU NF-PRO Project FI6W-CT-2003-02389. [9] Arcos, D., Hernán, P., De La Cruz, B., Herbert, H.-J., Savage, D., Smart, N.R., Villar, M.V., Van Loon, L.R. 2008: NF-PRO RTDC-2 Synthesis Report, Deliverable (D-N°:D2.6.4) EU NF-PRO Project FI6W-CT-2003-02389. [10] Villar et al. 2008: RTDC-3 Synthesis Report. EU NF-PRO Project FI6W-CT-2003-02389. [11] Aranyossy J-F., Mayor, J.C., Marschall, & Plas, F. 2008: EDZ development and evolution. RTDC-4 Synthesis Report. EU NF-PRO Project FI6W-CT-2003-02389. [12] Johnson, L. et al. 2008: RTDC-5 Synthesis Report, Deliverable (D-N°:5.2.3), EU NF-PRO Project FI6W-CT-2003-02389. 222
PANEL DISCUSSSION Summary of the Panel Discussion Concluding Session VI: Near-field processes Panel members and authors: Simon Loew (Chair), ETH Zürich, Switzerland Peter Blümling, NAGRA, Switzerland Lawrence Johnson, NAGRA, Switzerland Karl Lemmens, SCK-CEN, Belgium David Savage, Quintessa Ltd, United Kingdom Pierre Van Iseghem, SCK-CEN, Belgium This report summarizes the views of an expert panel on key remaining research issues in near-field processes which are critical for the long term safety of the geological disposal of high level radioactive wastes. The panel first met on the occasion of the Euradwaste '08 Conference and later continued the discussion in order to create this summary report. The questions put forward for discussion were: � Is there a common understanding of the most important safety functions of the Engineered Barrier System (EBS) in a HLW repository in salt, clay and granite? How would co-location of different waste types (e.g. HLW and L/ILW) influence these safety functions? � Which time scales should be considered in the detailed study of these safety functions? What are the contributions and limitations of “long-term” laboratory and in-situ experiments? � Which (coupled) processes, parameters and boundary conditions critical for these safety functions need further research? � What is the impact of physical and chemical heterogeneity of key properties of the EBS on the performance of the individual barriers at site scale? � How can we demonstrate that THMC coupled processes reach stable steady state conditions during the first 10’000 years and that we can describe them reliably? � Which implementation oriented studies need to be addressed in future research projects? Which key R&D stakeholders should have which function in the development of such projects? Safety Functions of the Engineered Barrier System The initial idea of the panel was to relate open research questions to safety functions of the engineered barrier system (EBS), which is composed of waste form, canister, overpack/buffer and seals, surrounded by the host rock in the immediate neighbourhood (i.e. the near-field). However, this idea had to be abandoned, because, due to differences in host rock properties and repository concepts, there are different requirements on the performance of the EBS, and therefore the safety functions of the EBS are differently defined in the national programmes. This even holds for safety functions attributed to the EBS in similar host rocks. 223
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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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Page 190 and 191: in the European coordinated action
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Page 194 and 195: 4. Discussion Tests with dissolved
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Page 202 and 203: tion of the column [2]. Moreover, t
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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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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
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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
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Page 236 and 237: 7. EDZ characterization and evoluti
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
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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
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Page 286 and 287: 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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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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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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