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Figure 3: Left: Spent fuel surface exposed 150 days to humid argon. Middle: Fuel surface resulting from a fresh cut made in the same rodlet. Right: Fuel surface after exposure to humid H2. In addition to surfaces, also gaseous and aqueous phases were analysed by mass spectrometry. A gas pressure increase was observed in all cases. It was 0.3 – 0.5 bar during the test under argon Under hydrogen, the total pressure increase was lower (0-0.2 bar (H2/Ar); 0.1-0.2 bar (H2)). The main gas component was in all experiments fission gas Xe. Under argon, radiolytically produced H2 was also detected. A possible explanation for the high fission gas release could be the opening of pathways for release from pressurized gas bubbles in the fuel. The oxygen content in all gas samples was below the detection limit (
The studies on alpha-doped UO2 have been performed on samples with damage corresponding to spent UO2 fuel after 10000 years of storage. Regarding the stability of the spent fuel the preliminary conclusion is that, while it is not expected that overall the fuel will lose its mechanical integrity, the alpha-damage and the precipitation of helium in regions with low porosity or few pre-existing trapping sites (bubbles) produced during irradiation might lead to a potential micro-cracking and local loss of cohesion. This is particularly the case for the high temperature region of irradiated fuels. The experiments on spent fuel evolution in steam have produced evidence that the presence of hydrogen leads to a reduced matrix alteration also under moist atmosphere conditions. 5. Acknowledgements This project has been co-funded by the European Commission and performed as part of the sixth Euratom Framework Programme for nuclear research and training activities (2002-2006) under contract FI6W-CT-2003-02389. The authors wish to thank Matthew Barker, National Nuclear Laboratory, UK, and Chris Chatwin, Sellafield Ltd, for supporting the use of the irradiated fuel samples and provision of PIE data. References [1] R.J. White, S.B. Fisher, P.M.A. Cook, R. Stratton, C.T. Walker, I.D. Palmer, J. Nucl. Mater. 288 (2001) 43. [2] S.B. Fisher, R.J. White, P.M.A. Cook, S. Bremier, R.C. Corcoran, R. Stratton, C.T. Walker, P.K. Ivison, I.D. Palmer, J. Nucl. Mater. 306 (2002) 153. [3] W.J. Gray, D.M. Strachan, Mat. Res. Soc. Symp. Proc. 212 (1991) 205. [4] W.J. Gray, L.E. Thomas, Mat. Res. Soc. Symp. Proc. 333 (1994) 391. [5] W. Gray, Mat. Res. Soc. Symp. Proc. 556 (1999) 487. [6] B. Hanson, Mat. Res. Soc. Symp. Proc. 824 (2004), 89-94. [7] D. Roudil, C. Jégou, V. Broudic, B. Muzeau, S. Peuget, X. Deschanels, J. Nucl. Mater. 362 (2007) 411. [8] N.C. Garisto, L.H. Johnson, W.H. Hocking, 2 nd Int. CANDU Fuel, Oct. 1989, 352. [9] L. Johnson, C. Ferry, C. Poinssot, P. Lovera, J. Nucl. Mater. 346 (2005) 56. [10] R.J. Finch, E.C. Buck, P.A. Finn, J.K. Bates, Mat. Res. Soc. Symp. Proc., 556 (1999) 431. [11] P. Taylor, D.D. Wood and D.G. Owen, J. Nucl. Mater. 223 (1995) 316. [12] P.C. Burns, R.J. Finch, D.J. Wronkiewicz, Direct Investigations of the Immobilization of Radionuclides in the Alteration Products of Spent Nuclear Fuel, Final Report, U.S. Department of Energy, Proj. 73691, 2004. [13] J.C. Cunnane, CSNF Waste Form Degradation: Summary Abstraction, ANL-EBS-MD- 000015 REV 02, Aug. 2004. 487
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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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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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Page 464 and 465: ous reasons, SCK•CEN chose to foc
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Page 476 and 477: 2. Methodology In the case of cylin
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Page 506 and 507: 1. Data compilation and evaluation
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Page 510 and 511: An overview of the test procedure w
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Page 514 and 515: The works performed within RTDC-1 p
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Page 520 and 521: The Ruprechtov natural analogue sit
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Page 528 and 529: from 12.5 to 13.5, have high ionic
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Page 536 and 537: 2. SAPIERR I and II In Europe, the
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Page 544 and 545: 2. Methodology Based on existing da
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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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