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A project would be justified to determine the underlying sorption processes. It would reflect that national programmes are reaching a state of development where coming closer to implementation requires generation of a more acceptable base for sorption assessment. Such a project would build on the very broad existing competence. It would also benefit from the use of advanced analytical techniques, especially recent developments where the spatial resolution is rapidly improving for determination of elemental composition and chemical states on different solids/minerals involved. Finally, the access to very elaborate site-specific data available through recent site characterization programmes provides for direct natural analogue / real system comparison and verification. 2. In-depth interpretation and integration of existing data from the large FP6 Disposal IP’s in view of the application to the Safety Case. FP6 disposal investigations build around the waste emplacement technology, near-field and farfield processes, and Performance Assessment (PA)/ the Safety Case. These IP’s complementary to each other are ESDRED, NF-PRO, FUNMIG and PAMINA. Each of these Integrated Projects deals with SC Topics, either with reference to the technology or science areas dealt with or certain PA/SC aspects. The outcome is implemented in present advanced national programmes. An added value may be expected from synthesizing the outcome of these four IP’s with respect to providing (i) an overall view of the outcome in terms of the advances in the state of knowledge for European national programmes at their different levels of development, (ii) an evaluation and prioritisation of the open issues identified in the list of suggestions for further work and (iii) conclusions and recommendations for future Euratom disposal programme activities. The latter two aspects are important elements also in building a disposal technology platform, presently under development. 3. Geochemical in-situ experiments, micro analytics In order to increase confidence in the performance assessment of nuclear waste disposal, verification of the speciation of radionuclides through in situ measurements is an important issue. Indeed, the computation of the migration of radionuclides in the near-field and far-field rely on thermodynamic databases, based on compilations and surface laboratory experiments. Direct or indirect evidence of in situ speciation have seldom been gathered. Taking advantage of existing underground laboratory facilities, it is a real challenge to be able to confront measurements and predictions. Recent progress in analytical chemistry (spectroscopy, electrochemistry) renders this goal achievable. 4. Isotopic dilution and exchange For mobile fission products, which mostly contribute to the impact of nuclear waste disposal, it is relevant to increase the safety margins by looking at processes that should be able to induce a significant retardation effect. Isotopic dilution and exchange are possible processes and need to be confirmed. This is especially true for 14 C, 36 Cl and 129 I. Theoretical studies, together with laboratory studies and field studies are necessary to document such processes. Retardation processes for mobile fission and activation products ( 79 Se, 129 I, 14 C…) including mineral reactions and nuclides The principal radionuclides migrating through the geological barrier in recent Safety Cases (SC) treating disposal concepts in clayrock formations are 129 I, 36 Cl, 79 Se, 41 Ca (Andra, 2005), 129 I, 36 Cl, 79 Se, 14 C organic (Nagra, 2002) and 129 I, 79 Se, 99 Tc (NIROND, 2001). In all cases except 41 Ca, this is a result of attributing them retardation values of 1 (Kd = 0). On the other hand, for certain of these radionuclides ( 79 Se, 129 I and 14 C organic) it is possible to hypothesize mechanisms which 364
might result in a slight, but potentially significant, retardation. Certain of these were brought out during the International Workshop on Fission and Activation Products in Nuclear Waste Disposal (16-19/1/2007, La Baule, FR) among which were Se immobilization by ferrous iron sorbed on clay, Se(II) sorption onto pyrite, exchange of 129 I with natural iodine pool… While existing SC show that the corresponding radioactive waste disposal concepts remain well within the required safety limits, additional safety margins, and increased confidence in the safety demonstration would be gained should research be able to show the capacity of such processes to retard migration of these radionuclides. 365
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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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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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Page 344 and 345: ganic/organic colloids”; WP 4.5
Page 346 and 347: Figure 1: Schematic of the FEBEX dr
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Page 350 and 351: Colloid Concentration (ppm) 160 140
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Page 354 and 355: References [1] Retrock (2005). Trea
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Page 360 and 361: The Ruprechtov site, located in the
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Page 364 and 365: exists as a stable mineral phase in
Page 366 and 367: pared to other sites with SOC-beari
Page 368 and 369: [3] Hauser, W. Geckeis, H., Götz,
Page 370 and 371: The science and technology group, r
Page 372 and 373: FEPCAT RTDC 1 RTDC 2 RTDC 3 Clay-ri
Page 374 and 375: 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
Page 390 and 391: lower depths are less saline. For t
Page 392 and 393: [3] Marivoet, J., Beuth, T., Alonso
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Page 396 and 397: A simplistic summary might place PA
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Page 408 and 409: 2.2.3 Graphical methods Let us call
Page 410 and 411: 3. The sensitivity analysis benchma
Page 412 and 413: 4. Discussion and conclusions Three
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Page 416 and 417: 2. Methodology The project particip
Page 418 and 419: Closely related to this proposal on
Page 420 and 421: 4.3 Structure The TP structure must
Page 422 and 423: 4.5 Implementation It is proposed t
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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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