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Phase-Out TRU Transmutation Scenarios studies based on Fast Neutron ADS Systems, E. Gonzalez and M. Embid-Segura. 7th NEA Information Exch. Meeting on Actinide and Fission Product P&T, Jeju (Republic of Korea), 14-16 October 2002. [19] Partitioning and Transmutation Potential for Waste Minimization in a Regional Context, Salvatores M. et al., 8th NEA Information Exch. Meeting on Actinide and Fission Product P&T, University of Nevada, Las Vegas 9-11 November, 2004. [20] Impact of Advanced Fuel Cycle Scenarios on Geological Disposal. J. Marivoet et al.. Proc. <strong>Euradwaste</strong> <strong>'08</strong> Conference (2008). 140
Impact of Advanced Fuel Cycle Scenarios on Geological Disposal Summary Jan Marivoet 1 , Miguel Cuñado 2 , Simon Norris 3 , Eef Weetjens 1 1 SCK·CEN, Mol, Belgium 2 Enresa, Madrid, Spain 3 NDA RWMD, Harwell, United Kingdom The impact of advanced nuclear fuel cycles on radioactive waste management and geological disposal has been evaluated within the Red-Impact project. Five representative fuel cycles, which were considered in equilibrium, were identified and the resulting waste volumes and compositions were estimated. Repository designs for disposal in hard rock and clay formations, developed by national radioactive waste management agencies for today's waste types, were used as reference concepts. After a 50 years cooling time, the heat generated in the highlevel radioactive waste arising from advanced fuel cycles is significantly lower than that in spent fuel from the present "once through" fuel cycle. This would allow the dimensions of a geological repository to be comparatively reduced. The impact of advanced fuel cycles on the radiological consequences in the case of the expected evolution or reference scenario is rather limited. This is because the maximum dose in this scenario, which is calculated to occur a few tens of thousands of years after the disposal of the waste and is associated with radionuclide transport in groundwater, is essentially due to mobile fission and activation products; as geological disposal systems are very effective at retarding the migration of actinides, the contribution of the actinides to the effective dose is limited. The associated intermediate-level waste contains considerable amounts of mobile activation products; these species persist in giving relatively high post-closure doses. On the other hand, for the variant human intrusion scenario, calculated doses to a geotechnical worker resulting from inadvertent intrusion into a high-level waste repository are significantly reduced in the case of advanced fuel cycles, because of the much lower actinide content of the waste. However, it should be noted that the realism of human intrusion scenarios, and the weight that could be placed on the associated outcome, is strongly debatable. 1. Introduction During the last 15 years, various studies investigating the role and feasibility of partitioning and transmutation (P&T) within nuclear fuel cycles have been carried out. The European Commission (EC) has initiated several research projects within its various framework programmes on the possibilities of applying P&T techniques to reduce the inventories of long-lived isotopes in radioactive waste [1,2]. The final objective of these EC-funded research projects is to lay the groundwork for future sustainable nuclear fuel cycle strategies involving transmutation in a dedicated waste-burning accelerator driven system (ADS) or in future Generation IV fast neutron reactors (FR). The Nuclear Energy Agency (NEA) has conducted a series of studies on P&T systems [3-5], which focused on a review of the progress in the separation of long-lived actinides and fission products, the options for their transmutation, and the possible benefit for the management of the radioactive waste. The International Atomic Energy Agency (IAEA) has published reports on the implications of P&T on nuclear fuel cycles and waste management [6,7]. Within the Generation IV International Forum [8], 141
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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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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
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Page 122 and 123: significantly reduce the quantities
Page 124 and 125: Pyrochemical processes rely on refi
Page 126 and 127: Figure 3: Schematic layout of an el
Page 128 and 129: Considering pyrochemistry technolog
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Page 132 and 133: Table 1: Fuels irradiated in the SU
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Page 136 and 137: Figure 6: Principle design characte
Page 138 and 139: Table 6: FUTURIX FTA fuels Fuel nam
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Page 142 and 143: After a review of the present statu
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Page 148 and 149: high level waste at the considered
Page 150 and 151: Pu or M.A. by the time it is needed
Page 152 and 153: of U and Pu only. P&T could complem
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Page 158 and 159: 10 nuclear nations (Argentina, Braz
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Page 162 and 163: A1 3.79E+08 270 7.12E-07 A2 3.51E+0
Page 164 and 165: nuclear fission in the reactors. Th
Page 166 and 167: 5. Conclusions The HLW arising from
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Page 170 and 171: tinides (MA) are destined for geolo
Page 172 and 173: [3] Enrique González: Head of Nucl
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Page 178 and 179: erage level of funding of research
Page 180 and 181: Prior to NF-PRO, the question wheth
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Page 190 and 191: in the European coordinated action
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Page 194 and 195: 4. Discussion Tests with dissolved
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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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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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