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Zones around such openings which exhibit altered properties are called the excavation damaged zone (EDZ) or excavation disturbed zone (EdZ). The definition of these technical terms was provided during the Cluster Conference “Impact of the excavation disturbed or damaged zone (EDZ) on the performance of radioactive waste geological repositories” in Luxembourg in November 2003 by Bernier et al. (2005) [1], stating that: (1) the excavation disturbed zone (EdZ) is the zone where only reversible mechanical and hydrological processes occur without resulting in major changes in flow and transport properties, while (2) the excavation damaged zone (EDZ) is a zone with significant irreversible processes and significant changes in flow and transport properties. These changes may result in a several orders of magnitude increase in flow permeability and enhanced flow along preferential flow paths, thus creating a significant impact on the performance of a repository. Thus, the EDZ may be relevant with respect to the long-term safety of a repository, but not the EdZ. The potential influence of the EDZ on safety was the reason for a number of very comprehensive experiments in underground laboratories in different host rocks such as crystalline rocks, clays, claystones, argillite and salt. It became clear that the creation of the EDZ during the construction process is important, but that changes during ventilation, heat generation by the waste and the resaturation process are also crucial for the evaluation of its impact on repository performance. Recently, the EC supported integrated project on near-field processes (NF-PRO) was completed allowing important conclusions [2] to be drawn regarding the creation and development of such zones. Active EC projects within the 6 th Framework Programme – TIMODAZ (Thermal Impact on the Damaged Zone around a Radioactive Waste Disposal in Clay Host Rocks) and THERESA (Thermal-Hydrological-Mechanical-Chemical Processes for Application in Repository Safety) – are underway, focusing on thermally induced changes around repository structures. 2. Methodology The evaluation of the influence of the EDZ on repository safety requires investigation of different stages in the lifetime of a repository: Construction phase: Stress redistribution and interaction with natural inhomogeneities lead to the creation of the EDZ. Rock strength and material anisotropy control the size and seriousness of the damaged zone. Further important factors are related to the construction process, including the applied excavation method, the speed of excavation and the rock support measures. Transition phase: The ventilation of the tunnels and the associated changes in relative humidity may alter the rock. After waste emplacement, the resaturation of the near-field (host rock and buffer) will take place; at the same time, heat-generating waste will lead to thermal loading of the near- and far-field. In addition, corrosion of the canisters will cause gas generation. Long-term phase: Human-induced disturbances of stress, pore pressure and temperature will disappear. On the other hand, the gas overpressures due to corrosion of the canisters and degradation of organic matter could enhance the expulsion of contaminated porewater along the backfilled tunnels and the EDZ. Furthermore, hydro-chemical couplings in the tunnel near-field, such as redox phenomena and cementwater/rock interactions could change the flow and transport properties of the EDZ. 204
The evaluation of EDZ behaviour in repositories is based on: Laboratory investigations In-situ tests in underground rock laboratories Material constitutive laws Conceptual modelling Numerical modelling 2.1 Laboratory investigations Laboratory investigations are carried out on rock samples either from boreholes mainly drilled using the double or triple core barrel technique or from blocks collected during tunnel excavation and conditioned with special care. Samples from clay formations need special treatment to avoid alteration of the rock due to unloading, drying or swelling and different techniques and equipment have been developed for this purpose. a) b) c) Deviatoric XRCT Consolidation T° loading XRCT loading 1 2 4 n Permeability measurement Figure 2.1: a and b) Examples of new triaxial hollow cylinder test equipment from ENPC (a) and GRS (b) which allow simulation tests to be carried out with mechanical and thermal loading similar to the evolution that will be encountered around disposal galleries for heat-emitting radioactive waste. c) During the tests, different techniques are used to study the fracturing and the sealing/healing processes under different THM conditions (μCT, XRCT, water/gas permeability measurements, etc.). After sample preparation, standard tests (e.g. uniaxial or triaxial compression tests, oedometer tests, creep tests) are carried out, but more sophisticated tests are required for adequately simulating the stress paths which are representative for EDZ development in a repository. Figure 2.1 shows the 205 hollow sample inner packer central heater outer jacket inlet (gas / water) 3 axial load axial load hollow cylideric sample outlet (gas / water) filter extensometer temperature sensor outer heater pressure / volume oil pump
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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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Page 222 and 223: layout of cells developed by ENPC w
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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
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Page 256 and 257: 2. Methodology In general, the work
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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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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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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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