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[6] Miehe, R., Kröhn, P., Moog, H., (2003): Hydraulische Kennwerte tonhaltiger Mineralgemische zum Verschluss von Untertagedeponien (KENTON). Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, Köln, GRS-193. [7] Rothfuchs, t., Jockwer, N., Miehe, R., Zhang, C.-l. (2005): Self-sealing Barriers of Clay/Mineral Mixtures in a Clay Repository SB Experiment in the Mont Terri Rock Laboratory Final Report of the Pre-Project, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, GRS-212 258
New Transport and Emplacement Technologies for Vitrified Waste and Spent Fuel Canisters Wilhelm Bollingerfehr 1 , Wolfgang Filbert 1 , Jobst Wehrmann 1 , Jean-Michel Bosgiraud 2 Summary 1 DBE TECHNOLOGY GmbH, Germany 2 ANDRA, France In the context of the Integrated Project “ESDRED” - Engineering Studies and Demonstration of Repository Designs [1] - funded by the European Commission, transport and emplacement technologies for radioactive waste packages were subject of industrial demonstration tests. Two national programmes - the German reference concept, which comprises the emplacement of spent fuel elements in self shielding casks in horizontal drifts and the emplacement of vitrified waste in deep vertical boreholes in a repository in salt rock, and the French concept, which considers the emplacement of vitrified waste into horizontal cells in a repository in clay (Argillites), were considered. In order to align the emplacement technologies for all categories of heat-generating waste, the emplacement of spent fuel elements in deep vertical boreholes was investigated as an alternative to the reference concept. For this alternative concept and for the French concept, suitable transport and handling equipment was developed, manufactured and will be tested under repository-relevant conditions on an industrial scale. This paper briefly describes both disposal concepts, presents the transport and emplacement systems developed for the waste packages of both emplacement concepts, and illustrates the set-up of the demonstration test facilities. First results of the demonstration programme are presented as well. 1. German reference concept for the disposal of heat-generating waste In Germany, rock salt was selected in the early 1960s as the preferred host rock for a repository for heat-generating waste because of its unique geohydrologic, thermal, and geomechanical properties as self-healing impermeable rock. A large number of salt domes with huge dimensions, many of them principally suitable to host a repository, exist in Northern Germany. In 1977, at the end of a time-consuming selection process, the salt dome in Gorleben was selected for further exploration regarding its suitability to host a repository for HLW. The corresponding reference concept for the disposal of heat-generating radioactive waste (Fig. 1) anticipates the emplacement of canisters containing vitrified waste in deep vertical boreholes, whereas spent fuel is to be disposed of in selfshielding POLLUX ® casks in horizontal drifts inside a salt mine [2]. The POLLUX ® casks, carbon steel casks weighing 65 tons each, are laid down on the floor of a horizontal drift at a depth of 840 m. The spaces between the casks and the drift walls are back-filled with crushed salt. In the vertical disposal concept, which allows a temperature of max. 200 °C at the contact surfaces between waste canisters and host rock, unshielded canisters with vitrified high-level radioactive waste (HLW) are emplaced in boreholes with a depth of up to 300 and a diameter of 60 cm. In order to facilitate the fast encapsulation of the waste by the host rock (rock salt), the boreholes are not lined. Obtaining a license to construct a repository in Germany requires previous demonstration to the competent authority that the level of protection (dose or risk) can be met with a high level of confi- 259
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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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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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Page 230 and 231: that provided by various national s
Page 232 and 233: system robustness, rather than as s
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Page 238 and 239: [4] Alonso, J. et al. 2004: Bentoni
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Page 246 and 247: 2. Methodology ESDRED has been focu
Page 248 and 249: Figure 3: Reduced scale mock-up aft
Page 250 and 251: Figure 8: Demonstration of emplacem
Page 252 and 253: The various reports produced by the
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Page 256 and 257: 2. Methodology In general, the work
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Page 260 and 261: Figure 3.2.1 Schematic representati
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Page 264 and 265: Figure 3.3.1 Emplacement of SF-Cani
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Page 268 and 269: the outlet with some pressure and f
Page 270 and 271: A experiment, using cross-hole seis
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Page 282 and 283: Figure 6: Sketch of the Pushing Rob
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Page 286 and 287: 1.1 Water Cushion Application SKB (
Page 288 and 289: In the case of SKB and Posiva, the
Page 290 and 291: Deposition machine tests with load
Page 292 and 293: Figure 10: Details of electrical pu
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Page 304 and 305: 2.3 Testing of low-pH shotcrete for
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Page 308 and 309: energy is produced by fission of ur
Page 310 and 311: 3.2. Integration 3.2.1. Pool Facili
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Page 316 and 317: Fig. 1.1: EU Member States involved
Page 318 and 319: Fig. 1.3: Stakeholders and interest
Page 320 and 321: - Present state of scientific level
Page 322 and 323: 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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366
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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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