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tions. This is a real dilemma: reliable and predictable cost calculations are required while at the same time cost estimates are subject to changes due to modified technical plans. Radioactive waste management is not a stand-alone industry. The technology to be used there is dependent on other industrial structures and their developments. It is impossible to foresee what will happen globally during the operation of a repository over the next 100 years or so. Issues like availability of raw materials, their prices and the existence of subcontractors can only be mentioned but no justified long-term predictions can be made. In addition, high level waste management schemes may encounter fundamental changes due to changes in the operational environment. This is suggested by recent international developments in the back-end of nuclear fuel cycle. References [1] Palmu J. (2008). Summary of the Cost Estimate for Spent Nuclear Fuel Disposal of the Olkiluoto (OL1-3) and Loviisa (LO1-2) Nuclear Power Plants. Memo POS-003662. Posiva Oy. 5 p. [2] DOE/OCRWM (2008). Analysis of the Total System Life Cycle Cost of the Civilian Radioactive Waste Management Program, Fiscal Year 2007. DOE/RW-0591. U.S. Department of Energy, Office of Civilian Radioactive Waste Management. 34 p + app. [3] SKB (2007). Plan 2007, Kostnader för kärnkraftens radioaktiva restproducter. Svensk Kärnbränslehantering AB. 56 p. [4] NDA (2008). Annual Report & Accounts 2007/08. Nuclear Decommissioning Authority. 187 p. [5] MITYC (2006). Sixth General Radioactive Waste Plan. Ministerio de Industria, Turismo y Comercio. 249 p. 56
PANEL DISCUSSION Summary of the Panel Discussion concluding Session II: Economical factors governing geological disposal programmes Panel members: Thibaud Labalette (Chair), ANDRA, France Milena Christoskova (Rapporteur), DPRAO, Bulgaria Hans D. K. Codée, COVRA, The Netherlands Vit�zslav Duda, RAWRA, Czech Republic Jean-Paul Minon, ONDRAF/NIRAS, Belgium Ján Timul'ák, DECOM A.S., Slovakia This report summarizes the outcome of session II on the economical factors governing geological disposal programmes. The session included a keynote speech by Dr Eero Patrakka (CEO, Posiva Oy, Finland) on the "Assessment of financial provisions for nuclear waste management – long-term perspective from a Finnish viewpoint". This was followed by a panel discussion based on a set of questions. The questions put forward for discussion were: � What are the main economic parameters governing RWM and disposal in the <strong>EU</strong>? � What are the main funding schemes and principles of financing waste disposal? � What are the main elements to consider in the overall estimation of RWM costs? � What are the influencing factors for costs variation? � What is the influence of the volume of waste on the disposal costs? � How can new decisions on nuclear energy (new NPP…) influence costs and funding schemes and how are they taken into account? The panellists presented their statements before the word was given to the floor. Hans D. K. Codée COVRA is a pioneer company in long-term management. If we make a simple calculation based on nuclear power units installed in the Netherlands, 30 years of operational period and energy production the cost of repository is unbearable for the country. Even if the operational period is doubled and new NPPs are constructed, the cost cannot be afforded in the country. The only opportunity is to share the repository and to share the costs. It is not easy but it is the European way. The fact the money will be kept for 100 years has to be accepted and the money has to be managed in a proper way. The volume of waste produced in France in one year is equal to the volume of waste produced in the Netherlands in course of 100 years. The operating cost depends on 57
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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
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 and 56: the first time in French history, a
Page 57 and 58: PANEL DISCUSSION Summary of the Pan
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: ferent, the technological solutions
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
Page 108 and 109: Europe's nuclear industries, theref
Page 110 and 111: filled - one key example being coll
Page 112 and 113: Table 2. FP6 Integrated Projects an
Page 114 and 115: EUROTRANS focuses on the transmutat
Page 116 and 117: 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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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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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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