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References [1] International Maritime Organization, Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter, [London Convention 1972], 1972 and 1996 Protocol Thereto. [2] Technical Appraisal of the Current Situation in the Field of Radioactive Waste Management. A Collective Opinion by the Radioactive Waste Management Committee, OECD/NEA, Paris, 1985. [3] Joint Statement on the Global Nuclear Energy Partnership and Nuclear Energy Cooperation, Washington, D.C., May 21, 2007, www.gnep.energy.gov/pdfs/GNEP_Joint_Statement.pdf. [4] F. Plas, P. Landais, The Phenomenological Analysis of Repository Situations (PARS) – Application Within the Dossier 2005 Argile (Meuse/Haute-Marne Site), in Safety Cases for Deep Geological Disposal of Radioactive Waste: Where Do We Stand? – Symposium Proceedings Paris, France, 23-25 January 2007 [5] Reversibility and Retrievability in Geologic Disposal of Radioactive Waste, NEA/RWM(2007)7, 08 March 2007 [6] Proposal for an International Reversibility-Retrievability Scale, Jean-Noël Dumont, Marie- Claude Dupuis, Jean-Michel Hoorelbeke, Thibaud Labalette, Gérald Ouzounian, 2008 International High-Level Radioactive Waste Management Conference, Sept. 7-11, 2008, Las Vegas, Nevada [7] Committee on Radioactive Waste Management, Managing our Radioactive Waste Safely, CoRWM’s recommendations to Government, CoRWM Doc. 700, July 2006 [8] La Mise en dépôt final, sur le territoire belge, des déchets radioactifs de faible et moyenne activité et de courte durée de vie, Rapport de clôture de l’ONDRAF relatif à la période 1985- 2006, invitant le Gouvernement fédéral à décider de la suite à donner au programme de dépôt, NIRON 2006-02F, mai 2006 [9] Consolidated version of the Planning Act No. 2006-739 of 28 June 2006 Concerning the Sustainable Management of Radioactive Materials and Waste (www.andra.fr/publication/produit/loi-VA-12122006.pdf) . 40
PANEL DISCUSSION Summary of the Panel Discussion Concluding Session I: Current Situation of Geological Disposal in the EU Panel members: Hans Forsström (Chair), IAEA Vienna Gheorghe Negut (Rapporteur), ANDRAD, Romania Michael Äbersold, SFOE Switzerland Alvaro Rodríguez Beceiro, ENRESA, Spain Vit�zslav Duda, RAWRA, Czech Republic Esko Ruokola, STUK, Finland This report summarizes the outcome of session I on the current situation of geological disposal in the EU. The session included a keynote speech by Mrs Marie-Claude Dupuis (CEO, ANDRA, France) as chairwoman of the OECD/NEA Radioactive Waste Management Committee (RWMC) on the global situation of geological disposal projects in the EU. This was followed by a panel discussion based on a set of questions. The questions put forward for discussion were: � What is the RWM situation in the EU Member States? � What are the success stories? � What are the obstacles for development of a solution? Policy? Public acceptance? Economics? � Is it possible to overcome wait-and-see approaches? � Long term storage: does it create or solve problems? � Are multinational solutions envisaged and/or desirable in the EU? � Who or what are the potential drivers? � Do we need binding EU legislation or can we count on voluntary measures? Apart from the presentation of the history and current status of geological disposal in the EU (see keynote paper), M.C. Dupuis insisted on the fact that intermediate storage cannot be considered as long-term solutions for high level radioactive waste and spent fuel. As well transmutation process will in any case produce high level waste. In conclusion, deep geological disposal remains the preferred option for management of high level radioactive waste and spent fuel. Implementation of geological disposal solutions requires parliamentary commitment on regulation and principles, as well as it necessitates social, technical and scientific cooperation. The panellists then presented their statements before the word was given to the floor. 41
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Interested in European research? Re
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LEGAL NOTICE Neither the European C
Page 7 and 8: TABLE OF CONTENTS FOREWORD iii CONF
Page 9 and 10: “Impact of advanced fuel cycle sc
Page 11 and 12: “Sensitivity analysis techniques
Page 13 and 14: Topic: Support actions SAPIERR-II -
Page 15: CONFERENCE SUMMARIES
Page 18 and 19: supported. The Commission believes
Page 20 and 21: Ms Monika Hammarström of SKB in Sw
Page 22 and 23: Dr Bruno of Amphos 21 urged the swi
Page 24 and 25: measurements of actinides to determ
Page 26 and 27: Dr Peter Blümling of Nagra in Swit
Page 28 and 29: Future directions There seemed to b
Page 31 and 32: 1. Introduction Keynote Address Pet
Page 33 and 34: tive waste management, a considerab
Page 35 and 36: the decision making process. The se
Page 37: All initiatives leading to encourag
Page 40 and 41: tegrating them as part of advanced
Page 43: General introduction and objectives
Page 47 and 48: Radioactive waste management: Where
Page 49 and 50: The intense development in nuclear
Page 51 and 52: Figure 3: Schematic diagram of the
Page 53 and 54: contributed to enhance knowledge ab
Page 55: the first time in French history, a
Page 59: With the support of IAEA preliminar
Page 63 and 64: Assessment of Financial Provisions
Page 65 and 66: collected in the cost of the nuclea
Page 67 and 68: erated by Fortum) and one PWR unit
Page 69 and 70: pected. As to tunnel backfilling, t
Page 71 and 72: ferent, the technological solutions
Page 73 and 74: PANEL DISCUSSION Summary of the Pan
Page 75: Discussion: As a response to a ques
Page 79 and 80: Cooperation in the development of g
Page 81 and 82: During the 1980’s it was realized
Page 83: government on the operating license
Page 86 and 87: tions. EDRAM is another example of
Page 88 and 89: Discussion: The chairman opened the
Page 91 and 92: Communicating the safety of radioac
Page 93 and 94: Communicating the Safety of Radioac
Page 95 and 96: Geological repositories … Differe
Page 97 and 98: Geological long-term stability (pla
Page 99 and 100: Times & doses in perspective (examp
Page 101 and 102: Trust is generated (by the regulato
Page 103 and 104: PANEL DISCUSSION Summary of the Pan
Page 105: 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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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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228
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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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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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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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