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10 nuclear nations (Argentina, Brazil, Canada, France, Japan, Korea, South Africa, Switzerland, UK and US) and Euratom (European Union) are working together to develop advanced reactor technologies for commercial deployment in the 2015 to 2030 timeframe. The main objective of the Red-Impact project was to evaluate the impact of the introduction of advanced fuel cycles for electricity generation on radioactive waste management, and, more specifically, on geological disposal. The project started in March 2004 and ended in September 2007. The project was divided into 6 work packages: (1) waste management and transmutation strategies, (2) industrial deployment scenarios, (3) assessment of waste streams, (4) waste management and disposal, (5) economic, environmental and societal assessment, and (6) synthesis and dissemination of results. The results obtained in the Red-Impact project are summarised in a synthesis report [9]. The outcomes of work packages 1 to 3 are presented at this conference by E. González [10]. The current paper gives an overview of the main results obtained within work package 4, which considered waste disposal in two hard rock formations, two clay formations and one salt formation. However, complete impact analyses were only done for one repository in granite (hard rock) and for one repository in clay. Therefore, this paper focuses on results obtained for those two repositories. 1.1 Considered fuel cycles During the first months of the Red-Impact project, work package 1 identified five representative fuel cycles, which were considered in equilibrium. These fuel cycles are: fuel cycle A1: the reference fuel cycle, which is the "once through" cycle based on pressurised water reactor (PWR) plants with uranium oxide fuel; fuel cycle A2: fuel cycle based on PWR plants with uranium oxide fuel, the generated Pu is recycled once as mixed oxide (MOX) fuel; fuel cycle A3: fuel cycle based on a sodium cooled fast neutron reactor with MOX fuels, in which Pu is multi-recycled; fuel cycle B1: fuel cycle based on a sodium cooled fast neutron reactor with MOX fuels, in which all the actinides are recycled; fuel cycle B2: fuel cycle based on PWR plants with uranium oxide fuel, the generated Pu is recycled once as MOX fuel, the minor actinides and the Pu in the spent MOX fuel are recycled in a fast neutron ADS. 1.2 Considered repository systems Repository designs for disposal in granite and clay formations developed by Spanish (Enresa) and Belgian (ONDRAF/NIRAS) national radioactive waste management agencies for today's waste types were used as reference concepts. The repository design considered for disposal in granite is a horizontal in-gallery disposal concept, which is shown in Fig. 1. The repository is assumed to be excavated in a generic granitic formation somewhere in Spain. The repository design considered for disposal in clay is described in detail in the SAFIR 2 report [11]. This reference repository is assumed to be excavated in the Boom Clay formation at the Mol site. At that site the host formation is about 100 m thick, of which an 80 m thick central zone is very homogeneous clay. The repository will have a central access facility consisting of at least two vertical shafts and two transport galleries. The disposal galleries will be excavated perpendicular upon the transport galleries. The high-level waste (HLW) and spent fuel (SF) canisters will be placed one after the other or with some spacing between two canisters (to respect temperature limitations) in 142
the centre of the galleries. A bentonite backfill will be placed between canisters and the gallery walls. Because the Boom Clay is a plastic clay, a concrete lining is required to avoid convergence of the gallery walls during the operational phase of the repository. As an example, Fig. 2 shows a scheme of a disposal gallery configuration for uranium oxide SF. DISPOSAL CONCEPT • Deep disposal • Crystalline rock • Carbon steel waste package • Horizontal emplacement • Bentonite buffer 143 Steel liner Bentonite blocks Waste package Figure 1: Longitudinal section of a disposal gallery (Spanish concept for disposal in granite). Figure 2: Gallery configuration for uranium oxide spent fuel disposal (SAFIR 2 concept [11] for disposal in clay). The functioning of geological disposal systems in granite or clay can be explained in relatively simple terms with the help of safety functions [11]: physical containment: a watertight container, also called overpack, is isolating the radioactive waste from groundwater during the strongly transient initial phase (re-saturation processes, heat
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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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Page 112 and 113: Table 2. FP6 Integrated Projects an
Page 114 and 115: EUROTRANS focuses on the transmutat
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Page 122 and 123: significantly reduce the quantities
Page 124 and 125: Pyrochemical processes rely on refi
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Page 128 and 129: Considering pyrochemistry technolog
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Page 132 and 133: Table 1: Fuels irradiated in the SU
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Page 138 and 139: Table 6: FUTURIX FTA fuels Fuel nam
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Page 142 and 143: After a review of the present statu
Page 144 and 145: suranium elements, “repository av
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Page 148 and 149: high level waste at the considered
Page 150 and 151: Pu or M.A. by the time it is needed
Page 152 and 153: of U and Pu only. P&T could complem
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Page 156 and 157: Phase-Out TRU Transmutation Scenari
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Page 162 and 163: A1 3.79E+08 270 7.12E-07 A2 3.51E+0
Page 164 and 165: nuclear fission in the reactors. Th
Page 166 and 167: 5. Conclusions The HLW arising from
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Page 170 and 171: tinides (MA) are destined for geolo
Page 172 and 173: [3] Enrique González: Head of Nucl
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Page 178 and 179: erage level of funding of research
Page 180 and 181: Prior to NF-PRO, the question wheth
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Page 190 and 191: in the European coordinated action
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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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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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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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