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Dr Bruno of Amphos 21 urged the swift implementation of the platform, saying, ‘Please, can everyone get on board as soon as possible [implying the research community alongside the radioactive waste management organisations]. The sooner we are ‘we’, the better off we will be.’ 6
Scientific and technical presentations The second part of the <strong>Euradwaste</strong> ’08 conference was dedicated to discussing the scientific and technical aspects of partitioning and transmutation, which aim to reduce the amount and toxicity of radioactive waste, the near- and far-field issues that impact the development of geological repositories, engineering studies, and aspects such as overall performance and safety assessment of these repositories. Approximately 270 scientists, engineers, politicians and regulators, and specialists in converging areas had a rare opportunity to hear about the state of play in the various disciplines related to radioactive waste management. Results from myriad FP6 (Sixth Framework Programme) projects were presented and future directions for projects funded under Euratom in FP7 were discussed. Because of the large spread of interest areas, and the limited time, the information imparted was for the most part quite general and easy to follow, and dialogue was encouraged. Occasionally time allowed projects to be reported in greater depth. Many of those who had attended the last <strong>Euradwaste</strong> conference in 2004 felt the panel discussions added a lot to their understanding of the issues and allowed for a meaningful level of dialogue. Partitioning and transmutation The technical part of the conference began with presentations on partitioning (chemical separation) and transmutation (radionuclide conversion) of the most radiotoxic long-lived radionuclides, which are carried out on spent fuel before disposal. Mr Ved Bhatnagar of the European Commission’s DG Research opened the session with a broad overview of these processes and followed up with a lively panel discussion on the effect of partitioning and transmutation (P&T) research on implementation of geological disposal. P&T research seeks to reduce the long-term radiotoxicity of nuclear waste to a few hundred years, rather than the tens of thousands of years of the initial spent fuel. This would serve two purposes: making the disposal of radioactive waste safer, in case of inadvertent human intrusion in a repository, and reducing the size of the repositories, if the heat-bearing radionuclides are removed. The research, as several presenters at the conference noted, does not seek to replace geological disposal as a waste management option, but to optimise it. Whether or not P&T is effective, geological repositories will be needed for the final product. ‘Dialogue between P&T and geological disposal communities is a goal of the European Commission,’ said Mr Bhatnagar. ‘It is also important to remember that P&T is necessary for developing sustainability in nuclear energy.’ Mr Enrique González Romero of CIEMAT in Spain explained that ‘spent fuel is a complex material with many kinds of radioactive isotopes with largely different characteristics. After partitioning, the idea is that each component will be used or treated separately.’ Mr Jean-Paul Glatz of the EC Joint Research Centre’s Institute for Transuranium Elements based in Germany gave an overview of research efforts in partitioning, which seeks to separate fission products and actinides that share very similar properties with one another. ‘We are still doing basic 7
Page 2 and 3: Interested in European research? Re
Page 4 and 5: 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 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 and 72: ferent, the technological solutions
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PANEL DISCUSSION Summary of the Pan
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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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PANEL DISCUSSION Summary of the Pan
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4. The regulators could play a very
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Europe's nuclear industries, theref
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filled - one key example being coll
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Table 2. FP6 Integrated Projects an
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EUROTRANS focuses on the transmutat
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consensus that geological disposal
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102
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104
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significantly reduce the quantities
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Pyrochemical processes rely on refi
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Figure 3: Schematic layout of an el
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Considering pyrochemistry technolog
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agreed for support through an integ
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Table 1: Fuels irradiated in the SU
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lead cooling (see Fig. 5). Alternat
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Figure 6: Principle design characte
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Table 6: FUTURIX FTA fuels Fuel nam
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124
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After a review of the present statu
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suranium elements, “repository av
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nificant fraction of fast reactors.
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high level waste at the considered
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Pu or M.A. by the time it is needed
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of U and Pu only. P&T could complem
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suranium elements, the thermal load
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Phase-Out TRU Transmutation Scenari
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10 nuclear nations (Argentina, Braz
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elease, strong radiation, pressure
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A1 3.79E+08 270 7.12E-07 A2 3.51E+0
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nuclear fission in the reactors. Th
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5. Conclusions The HLW arising from
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152
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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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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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