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elative intensity (cps) 8000 6000 4000 2000 0 mica (9.9 Å) kaolinite (7.12 Å) Qtz Qtz pyrite (1.63Å) YCW Qtz Qtz Qtz pyrite (1.92 Å) Qtz pyrite (2.7 Å) Qtz 0 20 40 60 °2theta (CuKα) Qtz 8000 6000 4000 2000 0 mica (9.9 Å) kaolinite (7.12 Å) Qtz 0 20 40 60 °2theta (CuKα) 514 Qtz 020 gypsum (7.56 Å) pyrite (1.63Å) ECW Qtz Qtz Qtz pyrite (1.92 Å) Qtz pyrite (2.7 Å) Qtz Qtz 0 days 90 days 180 days 360 days 510 days Figure 2: The unoriented specimen XRD patterns of the whole rock Boom Clay samples after 90, 180, 360 and 510 days of the interaction with YCW (Young Cement Water) and ECW (Evolved Cement Water). The uppermost XRD patterns correspond to the initial (undisturbed) Boom Clay sample. (1) FeS2 + 7/2 O2(aq.) + H2O � Fe 2+ + 2 SO4 2- + 2 H + (2) CaCO3 + H + � Ca 2+ + HCO3 - (3) Ca 2+ +SO4 2- + 2H2O � CaSO4. 2H2O The oxidation of pyrite is accompanied by a release of Fe 2+ , SO4 2- and acidity into the pore water. The acidity is buffered to a certain extent by the dissolution of calcite as inidicated by the reaction (2). In fact, the calcite was not detected in the clay close to the gallery lining in the samples from the Connecting Gallery, while it was present in the Test Drift. On the other hand, the jarosite was found exclusively in the clay core sampled in the Connecting Gallery. The absence of calcite in the core from the Connecting Gallery could point to a lesser buffering capacity of the Boom Clay at this place leading to a precipitation of jarosite, which is only possible at pH
the ECW from 12.5 at the beginning to as low as 5 after 510 days. The most extensive changes occurred in the mineralogy of clay phases interacted with the YCW, namely mixed-layered illitesmectite, kaolinite, chlorite and illite. The fact that the position of the XRD reflections of clay minerals are not changed with time in the alkaline batch experiment suggests that no clay mineral phase-to-phase transformation occurred, e.g. illitization of smectite, but rather dissolution was a dominant process. The dissolution is reflected in the decrease of the specific surface area (SSA) and decrease of the cation-exchange capacity (CEC) parameters. 5. Conclusions Comparing the two data sets from the Test Drift and the Connecting Gallery (HADES URL), the general conclusions could be drawn with respect to the degree and the extent of the oxidation at different times. The mineralogical evidence for the oxidation is traceable within the first ~4.5 cm ahead from the gallery lining both in the Test Drift and the Connecting Gallery. The gypsum as the most common oxidation product of pyrite was found in the both data sets, while the jarosite was found exclusively in the Connecting Gallery. This point to locally different geochemical conditions concerning Eh and pH in the Test Drift and Connecting Gallery. However, there is no mineralogical evidence to state that the ventilation could be an important factor affecting the extent of the oxidation in the the two studied cases. Therefore, the extent of the oxidation is determined by conditions or processes occuring during or soon after excavation, rather than during the ventilation of the galleries during the operational phase. The mineral stability of the Boom Clay depends on the initial base stregth of the applied alkaline solution. The YCW with the original pH of 13.2 induced more extensive mineral changes than the ECW having the initial pH of 12.5. The most significant changes in the mineralogy of Boom Clay caused by the alkaline plume perturbations involve the alteration of Na-Ca plagioclases to Kfeldpsars in the both studied cases and the dissolution of clay minerals (mainly mixed-layered illitesmectite phases) in the YCW. The dissolution of clays is accompanied by the decrease in the Cation Exchange Capacity and the Specific Surface Area parameters. The clay dissolution might increase the Boom Clay porosity and thus increase the hydraulic conductivity in the repository near-field. However, important to note is that based on modelling results of Wang et al. (2007 [4]), the extent of the alkaline plume disturbed zone in Boom Clay is very limited even after 100 ka. 6. Acknowledgements This project has been funded by the European Commission and performed as part of the sixth Euratom Framework Programme for nuclear research and training activities (2002-2006) under contract FI6W-028403. References [1] De Preter, P. (2007) The long-term safety functions within the disposal programmes of ONDRAF/NIRAS. ONDRAF/NIRAS note O/N 207-0526. [2] Wickham, S.M. (2005) The ONDRAF-NIRAS Supercontainer Concept. Galson Sciences, UK (2005). [3] NIROND. "SAFIR-2, Second safety Assessment and Feasibility Interim Report." NIROND, Brussels (2002). [4] Wang, L., Jacques, D., and De Cannière, P. (2007): Effects of an alkaline plume on the Boom Clay as a potential host formation for geological disposal of radioactive waste, SCK•CEN report, ER-28, first full draft, March 2007. 515
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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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PANEL DISCUSSION Summary of the Pan
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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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PANEL DISCUSSION Summary of the Pan
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4. The regulators could play a very
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Europe's nuclear industries, theref
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filled - one key example being coll
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Table 2. FP6 Integrated Projects an
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EUROTRANS focuses on the transmutat
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consensus that geological disposal
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102
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104
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significantly reduce the quantities
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Pyrochemical processes rely on refi
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Figure 3: Schematic layout of an el
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Considering pyrochemistry technolog
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agreed for support through an integ
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Table 1: Fuels irradiated in the SU
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lead cooling (see Fig. 5). Alternat
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Figure 6: Principle design characte
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Table 6: FUTURIX FTA fuels Fuel nam
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124
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After a review of the present statu
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suranium elements, “repository av
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nificant fraction of fast reactors.
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high level waste at the considered
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Pu or M.A. by the time it is needed
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of U and Pu only. P&T could complem
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suranium elements, the thermal load
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Phase-Out TRU Transmutation Scenari
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10 nuclear nations (Argentina, Braz
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elease, strong radiation, pressure
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A1 3.79E+08 270 7.12E-07 A2 3.51E+0
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nuclear fission in the reactors. Th
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5. Conclusions The HLW arising from
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152
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tinides (MA) are destined for geolo
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[3] Enrique González: Head of Nucl
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158
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160
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erage level of funding of research
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Prior to NF-PRO, the question wheth
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nant exchangeable cation. This chan
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eal concentration gradient in sampl
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access shafts, providing higher per
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172
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in the European coordinated action
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proved, with amongst others the det
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4. Discussion Tests with dissolved
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though with a slow rate. The data i
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surface. The coupling between water
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nuclear waste within the near-field
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tion of the column [2]. Moreover, t
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case, the iron diffusion front in t
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5.1 Sorption As an example of the t
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corrosion; up-scaling of clay alter
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Bentonite barriers are very importa
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To determine the impact of temperat
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in the underground laboratory in Gr
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under isothermal conditions. If the
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202
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Zones around such openings which ex
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layout of cells developed by ENPC w
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) a) e) d) f) d) e) f) c) Figure 3.
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EDZ removal by additional excavatio
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[7] Wenk H.-R., Voltolini, M., Mazu
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that provided by various national s
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system robustness, rather than as s
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Regarding diffusion studies perform
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7. EDZ characterization and evoluti
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[4] Alonso, J. et al. 2004: Bentoni
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There has been a significant change
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226
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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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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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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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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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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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