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the bottom of the heated press-mold the PM film (polyimide film) was placed and above it the mixture of crushed prepreg and resin. Pressing was conducted at 5 - 250 atm. Another variant envisaged mixing of crushed carbon with the resin containing the elements under study; then, molten binder was added on heating and stirring; the resulting mixture was transferred into the heated press-mold. Pellets were pressed at 300�� for 1 hour. It was found that among three variants of matrix production the third one is most feasible; in this case no prepregs should be preliminarily prepared. This method allows to avoid the non-controlled losses of investigated elements and to obtain sufficiently strong pellets. Besides, one can introduce nuclides in a carrier (ion-exchange resin, fullerene soot) as well as in any other solid chemical form, for example oxide. Table 1. Properties of composites containing VP-1AP Ratio of ITA-31: VP-1AP Properties of �-� composite Compression strength, MPa Modulus of elasticity, GP� Mass loss on carbonization, % 8 : 1 84 90 12 6 : 1 79 82 14 4 : 1 80 81 16 2 : 1 54 57 17 3.3 Leach rates of investigated elements Alongside the thermal and strength characteristics the leach rates of immobilized radionuclides or their chemical analogs are of significance in defining the chemical stability of matrices. In this work the leach rate was determined in accordance with the recommendations of the International standards. Distilled water was used as liquid phase; open surface area for different samples was 1.2 – 2.0 cm 2 . It is determined that the leach rates of rhenium from sample prepared on the basis of rhenium-saturated resin VP-1AP are 6.8×10 -5 – 1.7×10 -7 g/cm 2 ×day upon leaching during 1 – 90 days; of europium from sample prepared on the basis of SF-5 resin saturated with europium are 2.5×10 -5 – 1.6×10 -7 g/cm 2 ×day on leaching within the same time interval; of iodine from sample prepared on the basis of AB-17 saturated with iodide-ion are 4.8×10 -5 – 2.7×10 -6 g/cm 2 ×day. 3.4 Radiation stability of matrices. It is shown that irradiation of the matri�es by neutrons and gamma-irradiation in research reactor VVR-M in PNPI at neutron-flux density ~ 4·10 n/cm 2 ·s and integral flow ~ 10 18 n does not render the essential influence on their mechanical properties and leach rates of investigated elements. The values of these parameters for the samples after irradiation practically such, either as for samples before irradiation. 4. Conclusions The chemical analogues of such long-lived radionuclides as 99 Tc, 129 I, and 241 Am were immobilized. Rhenium, stable iodine and europium were used as the corresponding analogs, respectively. It was shown that the samples carbonized at temperatures up to 600-650°� possess high thermal stability. The produced samples exhibit high mechanical strength. Their compression strength varies 418
from 47 to 84 MPa, the modulus of elasticity from 49 to 90 GPa. The leach rates of rhenium, iodine and europium for different samples range between 2.5×10 -5 – 1.7×10 -7 g/cm 2 ×day. On the basis of the results obtained in this work strong matrices of high thermal, chemical and radiation stability for disposal of long-lived radionuclides can be developed. 5. Acknowledgments The work was carried out under financial support of International Science and Technology Centre (ISTC), Moscow (Project #2391). References [1] «Management of radioactive waste and spent nuclear fuel», MINATOM, Information and Analytical Collection, Moscow, 2000, issue 2, p. 90. [2] A.Fernandez et al. "Fuel/Target Concepts for Transmutation of Actinides". Proc. 6 th OECD/NEA Information Exchange Meeting on Actinide and Fission Product P&T (Madrid, Dec. 11-13, 2000). [3] Michael W. Cappiello, Dana C. Christensen «The Role of LANSE in the Nuclear Energy Future», Los Alamos Science, Number 30, 2006 [4] M.Ya.Goykhman et al. "Study of the mechanism high-temperature curing of polyimide ITA binders". Acta Montana, Series B , No 7 (1997) 9-19. [5] «Method of immobilization for long-lived radionuclides», M.K. Abdulakhatov, S.A. Bartenev, M.Ya. Goikhman et al. Patent application, Priority � 2007105656, G21F 9/16, G21F 9/23, Russia [6] ASTM Standard. C 1220-92, Standard Test Method for Static Leaching of Monolitic Waste Forms for Disposal of Radioactive Waste [7] ASTM Standard. C 1285-94, Standard Test Method for Determing Chemical Durability of Nuclear Waste Glasses: The Product Consistency Test (PCT) 419
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Interested in European research? Re
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LEGAL NOTICE Neither the European C
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TABLE OF CONTENTS FOREWORD iii CONF
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“Impact of advanced fuel cycle sc
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“Sensitivity analysis techniques
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Topic: Support actions SAPIERR-II -
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CONFERENCE SUMMARIES
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supported. The Commission believes
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Ms Monika Hammarström of SKB in Sw
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Dr Bruno of Amphos 21 urged the swi
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measurements of actinides to determ
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Dr Peter Blümling of Nagra in Swit
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Future directions There seemed to b
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1. Introduction Keynote Address Pet
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tive waste management, a considerab
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the decision making process. The se
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All initiatives leading to encourag
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tegrating them as part of advanced
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General introduction and objectives
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Radioactive waste management: Where
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The intense development in nuclear
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Figure 3: Schematic diagram of the
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contributed to enhance knowledge ab
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the first time in French history, a
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PANEL DISCUSSION Summary of the Pan
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With the support of IAEA preliminar
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Assessment of Financial Provisions
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collected in the cost of the nuclea
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erated by Fortum) and one PWR unit
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pected. As to tunnel backfilling, t
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ferent, the technological solutions
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Discussion: As a response to a ques
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Cooperation in the development of g
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During the 1980’s it was realized
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government on the operating license
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tions. EDRAM is another example of
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Discussion: The chairman opened the
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Communicating the safety of radioac
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Communicating the Safety of Radioac
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Geological repositories … Differe
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Geological long-term stability (pla
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Times & doses in perspective (examp
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Trust is generated (by the regulato
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4. The regulators could play a very
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Europe's nuclear industries, theref
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filled - one key example being coll
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Table 2. FP6 Integrated Projects an
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EUROTRANS focuses on the transmutat
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consensus that geological disposal
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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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366
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Page 386 and 387: The main goal of RTDC-1 is to provi
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Page 408 and 409: 2.2.3 Graphical methods Let us call
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Page 416 and 417: 2. Methodology The project particip
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Page 420 and 421: 4.3 Structure The TP structure must
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Page 432 and 433: materials. For attaining the stated
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Page 440 and 441: focuses on the study of the combine
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Page 446 and 447: 2.1 Laboratory experiment The dispo
Page 448 and 449: 3. Results 3.1 Laboratory experimen
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Page 452 and 453: 2. Experimental data 2.1 Laboratory
Page 454 and 455: sented in the accompanying poster,
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Page 458 and 459: situ stress to model the gallery ex
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Page 464 and 465: ous reasons, SCK•CEN chose to foc
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Page 468 and 469: [1] Bernier F., Li X.L., Weetjens E
Page 470 and 471: Concrete The cement used is an Ordi
Page 472 and 473: Brucite Ettringite 10 �m 8 �m F
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Page 476 and 477: 2. Methodology In the case of cylin
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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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